BIBLIOGRAPHY OF TECHNICAL CONTRIBUTIONS TO 

THE YUCCA MOUNTAIN PROGRAM BY THE CENTER 

FOR NUCLEAR WASTE REGULATORY ANALYSES, 

1988–2011 

Prepared for 

U.S. Nuclear Regulatory Commission 

Contract No. NRC 02–07–006 

Prepared by 

Jude McMurry 

Robert Pauline 

Center for Nuclear Waste Regulatory Analyses 

San Antonio, Texas 

September 2011 
ii 

ABSTRACT 

During its prelicensing activities to prepare for reviewing a license application for the proposed 

repository at Yucca Mountain, Nevada, and during subsequent licensing review activities, the 

U.S. Nuclear Regulatory Commission (NRC) sponsored more than 20 years of technical 

investigations that were conducted by the Center for Nuclear Waste Regulatory Analyses 

(CNWRA®). The prelicensing period ended in June 2008 when the U.S. Department of Energy 

(DOE) submitted a license application to NRC for authorization to construct a high-level waste 

geologic repository at Yucca Mountain, Nevada. Activities at CNWRA between 2008 and 

September 2010 focused on the technical analysis of DOE’s license application materials. 

Subsequently, CNWRA staff prepared more than 45 technical and programmatic knowledge 

management reports to document previously unpublished information or to synthesize staff 

technical insights gained from years of experience in the program. This bibliography, which is 

one of these knowledge management reports, provides a summary of the main technical reports 

and journal publications that were prepared by CNWRA staff between the establishment of 

CNWRA in 1987 and the orderly closure of the Yucca Mountain program in 2011. The scope of 

the bibliography is limited, for practical reasons, to (i) the key technical reports transmitted as 

deliverables to NRC, either by letter report format or as numbered CNWRA-series reports; 

(ii) published journal articles or book chapters, and, in some cases, (iii) manuscripts that were 

prepared for journals but were unpublished in the open literature. Annotations are provided for 

many of the items to summarize their contents or note their significance, and NRC accession 

numbers are provided for the reports and papers that are available from the NRC Agencywide 

Documents Access and Management System (ADAMS). 

 

 
iii 

CONTENTS 

Section Page 

ABSTRACT ................................................................................................................................... ii 

TABLES ....................................................................................................................................... iv 

ACKNOWLEDGMENTS ............................................................................................................... v 

1 INTRODUCTION ................................................................................................................ 1-1

1.1 Background ............................................................................................................... 1-1

1.2 Bibliography Components and Format ...................................................................... 1-3

2 OVERVIEW AND BACKGROUND REPORTS ................................................................... 2-1

3 CODE MANUALS, DESCRIPTIONS, AND USER GUIDES ............................................... 3-1

4 PRECLOSURE OPERATIONS AND SAFETY ................................................................... 4-1

5 POSTCLOSURE PERFORMANCE ASSESSMENT AND MODEL DEVELOPMENT ........ 5-1

6 SITE CHARACTERIZATION .............................................................................................. 6-1

7 IGNEOUS ACTIVITY .......................................................................................................... 7-1

8 STRUCTURAL GEOLOGY AND SEISMICITY ................................................................... 8-1

9 CLIMATE AND INFILTRATION .......................................................................................... 9-1

10 EVOLUTION OF THE NEAR-FIELD ENVIRONMENT ..................................................... 10-1

11 CORROSION OF ENGINEERED MATERIALS ................................................................ 11-1

12 STRUCTURAL PERFORMANCE OF ENGINEERED MATERIALS: 

CREEP, EMBRITTLEMENT, AND EARLY FAILURE MECHANISMS ............................. 12-1

13 ROCK MECHANICS AND EXCAVATION STABILITY ..................................................... 13-1

14 WASTE FORM PROPERTIES AND RADIONUCLIDE RELEASE ................................... 14-1

15 FLOW AND TRANSPORT ................................................................................................ 15-1

16 AQUEOUS AND VOLCANIC DOSE (BIOSPHERE) ........................................................ 16-1

17 SPECIAL PROJECTS ....................................................................................................... 17-1

17.1 Aluminum-Based Fuel Characteristics .................................................................... 17-1

17.2 West Valley .............................................................................................................. 17-1

17.3 Hanford Tank Waste Project ................................................................................... 17-2

APPENDIX—CNWRA-Series Reports: 1988–2008 

 
iv 

TABLES 

Table Page 

1-1 Key Technical Issues ..................................................................................................... 1-2 

1-2 Integrated Subissues ..................................................................................................... 1-2 

1-3 Key To Bibliography Entries for Documents Transmitted to NRC .................................. 1-4 

 
v 

ACKNOWLEDGMENTS 

This report describes work performed by the Center for Nuclear Waste Regulatory Analyses 

(CNWRA®) and its contractors for the U.S. Nuclear Regulatory Commission (NRC) under 

Contract No. NRC–02–07–006. The compilation of the bibliography is performed on behalf of 

the NRC Office of Nuclear Material Safety and Safeguards, Division of High-Level Waste 

Repository Safety. The technical activities reported in the bibliography listings were performed 

for the NRC Office of Nuclear Material Safety and Safeguards, Division of High-Level Waste 

Repository Safety, in support of the technical and regulatory topics related to a geologic 

repository for high-level nuclear waste, and for the NRC Office of Nuclear Regulatory Research 

and the NRC Office of Federal and State Materials and Environmental Management Programs 

in support of topics related to the storage and disposal of high-level nuclear waste. The report 

is an independent product of the CNWRA and does not necessarily reflect the view or regulatory 

position of NRC. 

The compilers of this bibliography gratefully acknowledge the advice and assistance of 

Maria Padilla, Laura Venhaus, and Leslie Gergen in collecting the reference information listed in 

the bibliography. The compilers also thank the many authors who provided annotations about 

their documents. Dr. James Rubenstone at the NRC initially suggested the preparation of a 

bibliography as a knowledge management activity, and he and other NRC staff provided helpful 

suggestions about how to organize the document. Dr. Bret Leslie at the NRC (and a former 

CNWRA scientist) has improved the usefulness of the bibliography by helping to identify many 

of the accession numbers for the CNWRA documents that are available for viewing in the NRC 

Agencywide Document Access and Management System (ADAMS). The compilers thank 

English Pearcy for the technical review, Budhi Sagar for the programmatic review, and 

L. Mulverhill for her editorial review. L. Selvey, A. Ramos, and B. Street are thanked for their 

administrative support. 

QUALITY OF DATA, ANALYSES, AND CODE DEVELOPMENT 

DATA: The CNWRA-generated data referenced in this bibliography meet quality assurance 

requirements described in the Geosciences and Engineering Division Quality Assurance 

Manual. Sources of other data should be consulted for determining the level of quality of 

those data. 

ANALYSES AND CODES: None. 
1-1 

1 INTRODUCTION 

1.1 Background 

In the mid-1980s, the U.S. Department of Energy (DOE) was in the process of characterizing 

several locations in the United States as potential sites for a geologic repository for disposal of 

the nation’s high-level radioactive waste. Anticipating the submission of a first-of-its-kind license 

application from DOE, perhaps as early as the mid-1990s, the U.S. Nuclear Regulatory 

Commission (NRC) recognized a need for support from a dedicated contractor that was free 

from conflict of interest to help NRC prepare to meet a statutory requirement to complete a 

review of the license application within the legislated 3-year period. To meet this need, the 

Center for Nuclear Waste Regulatory Analyses (CNWRA®) was established in October 1987 as 

a federally funded research and development center, sponsored by the NRC.1

 The main roles 

of CNWRA were to provide independent technical and scientific support to NRC (i) for the 

resolution of technical and regulatory issues related to a geologic repository for high-level 

nuclear waste and (ii) for other activities involved in the storage and disposal of high-level 

nuclear waste under the Nuclear Waste Policy Act. 

In December of 1987, shortly after the establishment of CNWRA, the U.S. Congress amended 

the Nuclear Waste Policy Act to specify that DOE site characterization activities for a geologic 

repository were to continue at only one potential site, at Yucca Mountain, Nevada. The main 

component of CNWRA work in the first few years was largely programmatic in scope. Staff 

contributed to a comprehensive evaluation of 10 CFR Part 60, which was the federal regulation 

in effect at that time for disposal of high-level radioactive waste in geologic repositories, and 

staff used insights from that work to identify regulatory, institutional, and technical uncertainties 

related to the licensing of a repository. Insights gained from this approach helped support NRC 

development of 10 CFR Part 63, a regulation specific to the disposal of high-level radioactive 

wastes in a proposed geologic repository at Yucca Mountain, and helped to identify a set of key 

technical issues that, beginning in the 1990s, were the basis of many subsequent CNWRA 

technical investigations and prelicensing interactions involving NRC, CNWRA, and DOE staff 

(Table 1-1). To prepare for the review of a license application, CNWRA technical work activities 

were reorganized in 2005 by a set of integrated subissues that conformed to the structure of the 

NRC formal review plan guidance (Table 1-2). 2 

The prelicensing period ended in June 2008 when the DOE submitted a license application to 

NRC for authorization to construct a high-level waste geologic repository at Yucca Mountain, 

Nevada. Subsequent CNWRA activities focused on support for the NRC acceptance 

review of the license application and the detailed technical analysis of DOE’s license 

application materials. 

 

 

1

CNWRA is a separate business entity of Southwest Research Institute (SwRI®), a not-for-profit research and 

development organization in San Antonio, Texas, that provides an internationally recognized research, engineering, 

and testing resource for industry, government, and small businesses. 

2

NRC. NUREG–1804, “Yucca Mountain Review Plan, Revision 2.” Washington, DC: NRC. July 2003. 
1-2 

Table 1-1. Key Technical Issues 

• Igneous Activity 

• Structural Deformation and Seismicity 

• Evolution of the Near-Field Geochemical Environment 

• Container Life and Source Term 

• Thermal Effects on Flow 

• Repository Design and Thermal–Mechanical Effects 

• Unsaturated and Saturated Flow Under Isothermal Conditions 

• Radionuclide Transport 

• Total System Performance Assessment and Integration 

Table 1-2. Integrated Subissues 

• Preclosure Safety 

• System Description and Demonstration of Multiple Barriers 

• Scenario Analysis and Event Probability 

• Degradation of Engineered Barriers 

• Mechanical Disruption of Engineered Barriers 

• Quantity and Chemistry of Water Contacting Engineered Barriers and Waste Forms 

• Radionuclide Release and Solubility Limits 

• Climate and Infiltration 

• Flow Paths in the Unsaturated Zone 

• Radionuclide Transport in the Unsaturated Zone 

• Flow Paths in the Saturated Zone 

• Radionuclide Transport in the Saturated Zone 

• Volcanic Disruption of Waste Packages 

• Airborne Transport of Radionuclides 

• Concentration of Radionuclides in Groundwater 

• Redistribution of Radionuclides in Soil 

• Biosphere Characteristics 

The technical analyses by NRC and CNWRA staff were documented in four NRC reports 

(NUREGs), one of which was published in 20103

 and the remaining three in 2011.4 During the 

technical analysis of DOE’s license application materials between 2008 and 2010, few other 

CNWRA technical documents were published. However, when CNWRA staff completed their 

 

3

NRC. NUREG–1949, “Safety Evaluation Report Related to Disposal of High-Level Radioactive at Yucca Mountain, 

Nevada.” Vol. 1, General Information. Washington, DC: NRC. August 2010. 4

NRC. NUREG–2107, “Technical Evaluation Report on the Content of the U.S. Department of Energy’s 

Yucca Mountain Repository License Application. Postclosure Volume: Repository Safety After Permanent Closure.” 

Washington, DC: NRC. August 2011. ML11223A273. 

NRC. NUREG–2108, “Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca 

Mountain Repository License Application.” Preclosure Volume: Repository Safety Before Permanent Closure. 

Washington, DC: NRC. September 2011. ML11250A093. 

NRC. NUREG–2109, “Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca 

Mountain Repository License Application.” Administrative and Programmatic Volume. Washington, DC: NRC. 

September 2011. ML11255A002. 
1-3 

contributions to the NRC technical evaluation reports in 2010 and 2011, many of the staff went 

on to prepare more than 45 technical and programmatic knowledge management reports that 

either documented previously unpublished information or synthesized staff insights gained from 

years of technical experience in the Yucca Mountain program. The purpose of this bibliography, 

which was compiled as one of the knowledge management reports, is to list the main technical 

and scientific documents that CNWRA staff have written over the years for NRC, from 

CNWRA’s establishment in 1987 through the NRC programmatic closeout of high-level waste 

activities related to Yucca Mountain in September 2011. 

1.2 Bibliography Components and Format 

Over more than two decades, CNWRA staff have transmitted literally thousands of draft and 

revised versions of programmatic and technical reports, journal manuscripts, conference 

papers, and workshop presentations to NRC. The scope of this bibliography is limited, for 

practical reasons, to a subset of these documents. The items selected for the bibliography are 

(i) the key technical reports transmitted as deliverables to NRC, either by letter report format or 

as numbered CNWRA-series reports; (ii) published journal articles or book chapters, and, in 

some cases, (iii) manuscripts that were prepared for journals but were unpublished in the open 

literature. Annotations are provided for many of the items, to summarize their content or note 

their significance. 

Programmatic, operational, and planning documents were excluded from the bibliographic 

listings, as were many hundreds of CNWRA technical abstracts and papers published only as 

conference proceedings. Despite the high technical quality of many of these proceedings, time 

and resources were not available to screen them individually, and including all of them would 

have made the bibliography unwieldy. 

The bibliography is organized by categories to facilitate its use as a technical resource. 

Several categories correspond closely to some of the programmatic divisions of work shown in 

Tables 1-1 and 1-2. Other bibliography categories are broader or more generic, to increase 

their usefulness for future investigators. A final category, Special Projects, is specific to sites 

besides Yucca Mountain, such as Hanford, Washington, and West Valley, New York, for which 

CNWRA supported radioactive waste-related topics for NRC. As an additional resource, an 

appendix to the bibliography provides a year-by-year listing of all CNWRA-series reports 

prepared for the high-level waste management repository safety program from 1988 to 2008. 

In general, the documents listed in the bibliography that were transmitted from CNWRA to NRC 

as reports are also publicly available in the NRC official recordkeeping system, the Agencywide 

Documents Access and Management System (ADAMS). Access to ADAMS is available online 

at www.nrc.gov/reading-rm/adams.html. Each document in ADAMS is identified by a unique 

accession number. If a document has been split into sections electronically to facilitate 

downloads from a remote location, each section will have a unique accession number. All of the 

ADAMS accession numbers for the documents listed in the bibliography begin with the letters 

“ML” followed by 9 digits. In a few cases, the reports and papers transmitted to NRC that are 

listed in the bibliography had not been assigned ML-accesssion numbers by the time the 

bibliography was compiled. However, those items can be retrieved with an ADAMS search on 

the title or author name. 

CNWRA maintains a separate document access system for internal use, the Electronic Library 

Facility (ELF), which contains a data record with a unique identifier for each project-related item 

transmitted from CNWRA to NRC. The ELF database was the primary resource used to 
1-4 

construct this bibliography, so the listed reports include a unique ELF identifier for each listing—

beginning with the letter “Q” and followed by 12 numerals—which corresponds to a set of 

records about the document and, in most cases, links to an electronic copy of the document 

itself. For CNWRA staff, it is typically simpler to access documents using ELF than by 

downloading the document from ADAMS, so the “Q” number is also included in the bibliographic 

listings, plus the project number that supported the work. 

Individual bibliography items are listed alphabetically by author name. Within each listing, the 

remainder of the formatting differs slightly depending on whether the item is a publication in the 

open literature or a document transmitted from CNWRA to NRC as a program deliverable. 

Table 1-3 provides an explanation of the format used in this bibliography for CNWRA reports 

and papers that were prepared for NRC as project-related items. 

Published journal articles and book chapters are formatted in the bibliography according to the 

CNWRA style guide, in which the typical sequence is as follows: 

Journal 

Author(s). “Title of Article.” Title of Journal. Volume number, issue number, page numbers. 

Year of publication. 

Chapter in Book

Author(s). “Title of Chapter.” Title of Book. Publisher City, Publisher State: Publisher Name. 

Year. 

Table 1-3. Key to Bibliography Entries for Documents Transmitted to NRC 

Entry Explanation 

Author(s) 

Transmittal date Date the document was transmitted from CNWRA to NRC 

(mm/dd/yyyy) 

Title Title of report or unpublished manuscript 

Report Number Optional. Numbered CNWRA reports use one of two 

sequences: “CNWRA yy-nnn” or “CNWRA yyyy-nnn” 

Status Optional. Final, Revised, etc. 

Publisher City and State San Antonio, Texas 

Publisher Center for Nuclear Waste Regulatory Analyses 

Publication Date Year, or Month and Year 

Annotation Optional. Short description of report or its significance, or other 

notes 

Project Number Identifies the project milestone number represented by the 

document 

ELF Identification Number Unique electronic locator for the CNWRA in-house document 

record; format is “Qyyyymmddnnnn” 

ADAMS Accession Number Listed where available. Unique electronic locator(s) for the 

document in the NRC document management system; format 

is “MLnnnnnnnnn” 

 
2-1 

2 OVERVIEW AND BACKGROUND REPORTS 

These are reports or papers that provide general information, cover a broad range of topics in a 

single document, or treat a specific topic (e.g., the Yucca Mountain Environmental Impact 

Statement) not covered elsewhere.

Ahola, M., R. Baca, A. Chowdhury, C. Connor, G. Cragnolino, F. Dodge, D. Dunn, 

A. Ghosh, R. Green, B. Hill, S. Hsiung, V. Kapoor, R. Manteufel, S. McDuffie, S. Mohanty, 

W. Murphy, R. Pabalan, E. Pearcy, N. Sridhar, G. Stirewalt, S. Stothoff, D. Turner, 

G. Wittmeyer, and S. Young. 02/01/1994. “U.S. Nuclear Regulatory Commission (NRC) 

High-Level Radioactive Waste Research at Center for Nuclear Waste Regulatory Analyses 

(CNWRA) for July through December 1993.” B. Sagar, ed. CNWRA 93-02S. San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses: February 1994. 

20.05704.004, Q199403180008, ML033650211 

Ahola, M., R. Baca, A. Bagtzoglou, A.H. Chowdhury, C.B. Connor, G. Cragnolino, D. Dunn, 

A. Ghosh, R. Green, B. Henderson, B. Hill, S. Hsiung, B. Leslie, R. Manteufel, R. Martin, 

S. Mohanty, W. Murphy, R. Pabalan, E. Pearcy, N. Sridhar, D.R. Turner, G.W. Wittmeyer, 

and S.R. Young. 08/12/1993. “U.S. Nuclear Regulatory Commission (NRC) High-Level 

Radioactive Waste Research at the Center for Nuclear Waste Regulatory Analyses (CNWRA) 

for January through June 1993.” B. Sagar, ed. CNWRA 93-01S. San Antonio, Texas: Center 

for Nuclear Waste Regulatory Analyses: August 1993. 

20.05704.004, Q199309200006, ML033650178 

Ahola, M.P., P. Angell, R.G. Baca, A.C. Bagtzoglou, C.B. Connor, F.M. Conway, 

G.A. Cragnolino, D.S. Dunn, D.A. Ferrill, A. Ghosh, B.E. Hill, S.M. Hsiung, M.S. Jarzemba, 

P.C. Lichtner, R.D. Manteufel, S. Mohanty, W.M. Murphy, R.T. Pabalan, E.C. Pearcy, 

D.A. Pickett, J.D. Prikryl, N. Sridhar, J.A. Stamatakos, S.A. Stothoff, D.R. Turner, and 

G.W. Wittmeyer. 02/23/1996. “U.S. Nuclear Regulatory Commission (NRC) High-Level 

Radioactive Waste Research at Center for Nuclear Waste Regulatory Analyses (CNWRA) for 

July through December 1995.” B. Sagar, ed. CNWRA 95-02S. San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. February 1996. 

20.05708.463/473/563/573/671, Q199603220007, ML040230584 

Ahola, M.P., R.G. Baca, F.P. Bertetti, A.H. Chowdhury, C.B. Connor, G.A. Cragnolino, 

D.S. Dunn, D.A. Ferrill, D.B. Henderson, B.E. Hill, S.M. Hsiung, D.D. Kana, R.V. Klar, 

P.C. Lichtner, R.H. Martin, S. Mohanty, A.P. Morris, W.M. Murphy, R.T. Pabalan, 

E.C. Pearcy, J.D. Prikryl, N. Sridhar, S.A. Stothoff, D.R. Turner, G.W. Wittmeyer, and 

B. Sagar. 02/01/1995. “U.S. Nuclear Regulatory Commission (NRC) High-Level Radioactive 

Waste Research at Center for Nuclear Waste Regulatory Analyses (CNWRA) for July through 

December 1994. B. Sagar, ed. CNWRA 94-02S. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses: February 1995. 

20.05704.002, Q199503060001, ML040210615 

 
2-2 

Ahola, M.P., R.G. Baca, F.P. Bertetti, A.H. Chowdhury, C.B. Connor, G.A. Cragnolino, 

D.S. Dunn, R.T. Green, D.A. Ferrill, D.B. Henderson, B.E. Hill, S.M. Hsiung, R.C. Lichtner, 

S. Mohanty, A.P. Morris, W.M. Murphy, G.l. Ofoegbu, R.T. Pabalan, E.C. Pearcy, 

N. Sridhar, G.L. Stirewalt, S.A. Stothoff, D.R. Turner, G.W. Wittmeyer, and S.R. Young. 

09/12/1994. “U.S. Nuclear Regulatory Commission (NRC) High-Level Radioactive Waste 

Research at the Center for Nuclear Waste Regulatory Analyses (CNWRA) for January through 

June 1994.” B. Sagar, ed. CNWRA 94-01S. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 1994. 

20.05704.002, Q199410040003, ML040230547 

Apps, J.A., J.W. Bradbury, R.E. Cady, R.C. Ewing, D.L. Gustafson, R.B. Hofmann, 

D.T. Hoxie, L.A. Kovach, M.B. McNeil, W.M. Murphy, W.R. Ott, E.C. Pearcy, B. Sagar, 

M.E. Shea, N. Sridhar, G.W. Wittmeyer, J.R. Wood, and S.R. Young. 09/05/1993. “The 

Role of Natural Analogs in Geologic Disposal of High-Level Nuclear Waste.” 

CNWRA 93-020. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 1993. 

20.05704.002, Q199311300002, ML040360540 

Baca, R.G., A.C. Bagtzoglou, D. Balin, F.P. Bertetti, C.B. Connor, F.M. Conway, D.A.Ferrill, 

C.J. Goulet, B.E. Hill, M.S. Jarzemba, R.V. Klar, P. LaFemina, P.C. Lichtner, A.P. Morris, 

W.M. Murphy, R.T. Pabalan, E.C. Pearcy, D.A. Pickett, J.D. Prikryl, K.H. Spivey, 

J.A. Stamatakos, S.A. Stothoff, D.R. Turner, and G.W. Wittmeyer. 08/01/1995. 

“U.S. Nuclear Regulatory Commission (NRC) High-Level Radioactive Waste Research at 

Center for Nuclear Waste Regulatory Analyses (CNWRA) January through June 1995 

(Semi-Annual Report).” B. Sagar, ed. CNWRA 95-01S. San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. August 1995 

20.5704.002, Q199601050013, ML040220368 

Bryan, H. and D.R. Turner. 10/26/2007. “Nevada Demographic Survey Information on 

Low-Income and Minority Populations in the Vicinity of Yucca Mountain, Nevada.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. October 2007. 

20.06002.01.151.720, Q200710260002, 

Cragnolino, G.A. and N. Sridhar. 09/30/1995. “Expert-Panel Review of the Integrated Waste 

Package Experiments Research Project.” CNWRA 95-020. San Antonio, Texas: Center for 

Nuclear Regulatory Analyses. September 1995. 

20.05704.044, Q199601050014, ML040220371 

 This report documents the review of the Integrated Waste Package Experiments 

research project conducted at CNWRA, by an independent panel of five experts in materials 

science, combining expertise in the areas of localized corrosion, stress corrosion cracking, 

thermal stability and microbially influenced corrosion. 

 
2-3 

DeWispelare, A.R., L.T. Herren, E.J. Bonano, and R.T. Clemen. 09/30/1994. 

“Background Report on the Use and Elicitation of Expert Judgment.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. CNWRA 94-019. September 1994. 

20.05704.712.405, Q199410110002, ML040230556 

The report addresses the use of both informal and formal expert judgment techniques, 

with emphasis on the latter. The report surveys historical and current use of expert judgment in 

the nuclear programs. The report also presents criteria to assess the quality of a formal expert 

elicitation procedure and issues affecting the use of the results of a formal expert elicitation. 

Hill, B.E. 03/01/1995. “Expert-Panel Review of CNWRA Volcanism Research Programs.” 

(Revised). CNWRA 95-002. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. January 1995. 

20.05704.123.050, Q200605080002, ML040220371 

This report describes how an independent panel of five experts in basaltic volcanology 

reviewed ongoing volcanism research programs at the CNWRA. The goals of this review were 

to (i) critically review the objectives and approaches of CNWRA volcanism research and its 

application to licensing issues at the proposed Yucca Mountain high-level waste repository site; 

(ii) recommend improvements to the research scope and methodologies, and investigate new 

issues that may not be part of the original research plans; and (iii) evaluate interpretations of the 

available data and explore alternative hypotheses. 

Juckett, M. 09/28/2011. “Evolution of NRC and Public Attitudes Regarding Public Outreach.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.112, Q201109280004, ML112710515 

 This knowledge management report, developed in collaboration with NRC staff, 

discusses the evolution of attitudes and technology over the duration of the NRC High-Level 

Waste Public Outreach Program. 

Juckett, M. 09/28/2011. “Lessons Learned From Public Outreach Meetings.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.110, Q201109280003 

 The public outreach program was vital to communication with stakeholders in the NRC 

license review process. The purpose of this knowledge management report is to retain, and 

make accessible for future use, a record of the approaches that were used in this program to 

convey information to the public. Much of this information is otherwise unrecorded because 

public outreach activities do not have the same formal documentation requirements as other 

technical activities. 

Juckett, M. 09/28/2011. “Media Used by U.S. Nuclear Regulatory Commission in Conveying 

Information to the Public.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2010. 

20.14002.01.441.104, Q201109280002 

 This knowledge management report describes the development and purpose of NRC 

public outreach materials and their reception by the public and stakeholders. 

 
2-4 

Juckett, M. 07/07/2006. “Safety Rules for a Potential High-Level Geologic Repository at 

Yucca Mountain, Nevada: What does the U.S. Nuclear Regulatory Commission Require?” 

20.06002.01.161.610, Q200607070007 

This publication is a public outreach document that provides background information 

about the Yucca Mountain licensing requirements. The NRC subsequently revised the 

document and produced the brochure under the title “Judging the Safety of a Repository at 

Yucca Mountain, Nevada” which is available at http://www.nrc.gov/waste/hlwdisposal/licensing/acceptance-safety/judging-safety.pdf 

Mackin, P. 02/22/2011. “Using SharePoint to Support Development of a Technical Evaluation 

Report.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. February 2011. 

20.14002.01.441.132, Q201102210003, ML110530163

Manteufel, R.D., M.S. Jarzemba, and R.G. Baca. 04/16/1996. “Relative Hazard of High-Level 

Waste Over Long Time Periods.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. 1996. 

20.05708.771.615, Q199606140001, ML061370637 

Mohanty, S. 06/11/2004. “High-Level Radioactive Waste Disposal.” Nuclear Technology. 

Vol. 148, No.2. Page 103. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. 2004. 

20.06002.01.112, Q200406170014 

This article was prepared as the introduction for a special issue of Nuclear Technology. 

Mohanty, S. 06/27/2003. “ Safety in the (Very) Long Run Assessing Long-Term Performance 

of a Geologic Nuclear Waste Disposal Site.” Technology Today. San Antonio, Texas: 

Southwest Research Institute. pp.10–15. July 2003. 

20.06002.01.112.300, Q200306300010 

Murphy, W.M. 08/21/1995. “Natural Analogs for Yucca Mountain.” Radwaste Magazine. 

Vol. 2. pp. 44–50. 1995. 

20.05704.064, Q199509210004 

Murphy, W.M. 05/20/1992. “Natural Analog Studies for Geologic Disposal of Nuclear Waste.” 

Technology Today. San Antonio, Texas: Southwest Research Institute. pp. 16–21. 

June 1992. 

20.03704.063, Q199206160005 

Nuclear Regulatory Commission. 12/16/2004. NUREG–1762, “Integrated Issue Resolution 

Status Report.” Volumes 1 and 2. Rev. 1. Washington, DC: U.S. Nuclear Regulatory 

Commission. April 2005. 

20.06002.01.181.410, Q200412200006, ML051360159 ML051360241 

Numerous other “Issue Resolution Reports” were prepared during the prelicensing 

period and dealt with specific key technical issues (Table 1-1) that had been identified by NRC 

and CNWRA staff. Many of those items are listed under specific subject categories elsewhere 

in the bibliography. The report cited here, a two-volume NUREG, summarizes all the 

Key Technical Issue agreements that had been reached as of 2004, after DOE had recently 

published a large number of supporting technical reports about a potential repository at 

Yucca Mountain. This NUREG, which was prepared with input from CNWRA staff, provides an 
2-5 

overview of the available information and resolution status of the technical issue agreements. 

The report also documents the risk insights developed by NRC and CNWRA staffs, the results 

of reviews of DOE reports, independent confirmatory work by NRC and CNWRA staffs, 

information from published literature, and other publicly available information.

Nuclear Regulatory Commission. 07/08/2003. NUREG–1804, “Yucca Mountain Review 

Plan.” Final Report, Rev. 2. Washington, DC: U.S. Nuclear Regulatory Commission 

July 2003. 

20.06002.01.171.315, Q200307080006, ML032030389 

This review plan, which was developed with input from CNWRA staff, provided guidance 

for the NRC staff to evaluate a U.S. Department of Energy license application for a geologic 

repository at Yucca Mountain. The principal purpose of the Yucca Mountain Review Plan was 

to ensure the quality, uniformity, and consistency of NRC staff reviews of the license application 

and any requested amendments. The Yucca Mountain Review Plan has separate sections for 

reviews of general information, repository safety before permanent closure, repository safety 

after permanent closure, the research and development program to resolve safety questions, 

the performance confirmation program, and administrative and programmatic requirements. 

Each section addresses determining compliance with specific regulatory requirements from 

10 CFR Part 63. The guidance in the Yucca Mountain Review Plan is risk-informed and 

performance-based to the extent practical. 

Pabalan, R.T. 09/28/1995. “Report on the Peer Review of the Sorption Modeling for 

High-Level Waste Performance Assessment Research Project.” CNWRA 95-023. San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. September 1995. 

20.05704.074, Q199510110003, ML040220328 

An independent panel of five experts in sorption studies reviewed ongoing radionuclide 

sorption research conducted by the CNWRA under the Sorption Modeling for High-Level Waste 

(HLW) Performance Assessment Research Project. The goals of the review were to (i) critically 

review the objectives and approaches of the CNWRA Sorption Research Project and its 

application to licensing issues at the proposed Yucca Mountain HLW repository site; 

(ii) recommend improvements to the research scope and methodologies, and identify new 

issues that may not be part of the original research plan; (iii) evaluate interpretations of the 

available data and explore alternative hypotheses; and (iv) help prioritize future activities taking 

into consideration resource and time constraints imposed on the project and anticipated 

programmatic schedules. This report discusses the procedure used in selecting the review 

panel members, presents an outline which the panel used as a guide for the review process, 

and summarizes the comments and recommendations of the review panel. 

Pabalan, R.T. 04/14/1994. “Summary Assessment of the Radionuclides Relevant to Research 

on the Geologic Disposal of High-Level Radioactive Wastes.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. 1994. 

20.05704.074.165, Q200310080001, ML033640286 

The potential release of radionuclides to the accessible environment is the key issue of 

concern in the design and licensing of a geologic repository. The HLW proposed to be 

emplaced in a geologic repository at Yucca Mountain comprised many different radionuclides. 

Limited programmatic resources and the expected complex chemistry and transport behavior of 

HLW radionuclides made it important to identify those radionuclides on which to focus research 

efforts. This summary assessment was conducted to consider what criteria should be used for 

selecting HLW radionuclides for NRC-sponsored research projects, and how this subset of 
2-6 

radionuclides could be used to screen (at least in a preliminary sense) relevant radionuclides for 

further study. 

Sagar, B., J. Stamatakos, and A. Ghosh. 09/21/2011. “The Center for Nuclear Waste 

Regulatory Analyses (CNWRA) Perspective on Prelicensing Interactions and Information 

Gathering.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 

2011. 

20.14002.01.441.182, Q201109210002, ML112640297 

Tschoepe, E., F.F. Lyle, Jr., D.M. Dancer, C.G. Interrante, and P.K. Nair. 06/01/1994. “Field 

Engineering Experience with Structural Materials.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. June 1994. 

20.05702.551, Q199406140004, ML033650222

The report summarizes information on three aspects pertaining to reliability of 

radioactive HLW packages for disposal: (i) reliability data for certain containers, (ii) corrosion 

engineering experience, and (iii) design and fabrication methodology. Data and information 

from various technical publications provided the basis for this report. 

Turner, D.R. and L. Canter. 05/19/2008. “The Use of Environmental Indicators for Impact 

Assessment in Compliance with the National Environmental Policy Act.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. May 2008. 

20.06002.01.151.725 (20.14002.01.051), Q200805200002, ML081410838 
3-1 

3 CODE MANUALS, DESCRIPTIONS, AND USER GUIDES 

Ababou, R., L.W. Gelhar, and C. Hemel. 04/06/1992. “Iterative Solution of Large Matrix 

Systems for Three-Dimensional Flow in Heterogeneous Geologic Media.” Cray Channels. 

1992. 

20.03704.052, Q199204090001 

 This article relates the BIGFLOW numerical processing code to the Cray computers that 

were used to implement the code. It was published in an industry trade magazine 

(Cray Channels). 

Baca, R. 05/01/1993. “Description of IPA Phase 2 Total System Code.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. 

20.05702.065.150, Q199306240002, ML040200553 

Bagtzoglou, A.C., R. Ababou, and A. Nedungadi. 12/10/1992. “BIGFLOW: A 

Multi-Dimensional Code Flow in Heterogeneous and Variably Saturated Geologic Media 

(Theory and User's Manual - Version 1.0).” CNWRA 92-026. San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. December 1992. 

20.05704.055, Q199212170011, ML040690221 

This report documents the underlying mathematical and numerical models, test 

problems, benchmarks, and applications of the BIGFLOW code. The report describes that the 

BIGFLOW software package is composed of a simulation code (BIGFLOW), and an interactive 

data processing code (DATAFLOW). The simulation code can be used for detailed modeling of 

transient or steady state flow systems in three-dimensional (3D) unsaturated, partially saturated, 

or saturated, heterogeneous porous media. BIGFLOW has been used for studying macroscale 

behavior of saturated and unsaturated flow processes in randomly heterogeneous media, for 

performance assessment of a high-level nuclear waste geologic repository in the presence of 

layers and faults, and for hydrologic simulations such as strip-source infiltration in layered soils 

or groundwater flow through lakes. A subsequent version (1.1) of BIGFLOW was documented 

in 1993 as NUREG/CR–6028, but that version was retired later the same year.

Connor, L., C.B. Connor, and B.E. Hill. 09/11/2002. “PVHA_YM Version 2.0 C Probabilistic 

Volcanic Hazard Assessment Methods for a Proposed High Level Radioactive Waste 

Repository at Yucca Mountain, Nevada.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 2002. 

20.01402.462.260, Q200209170003, ML033640083 

Dasgupta, B., R. Benke, T. Maxwell, and N. Eisenberg. 07/08/2003. “Preclosure Safety 

Analysis (PCSA) Tool Version 2.0 User Guide.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. June 2003. 

20.06002.01.103.310, Q200307080007, ML040350626 

 This report describes the preclosure safety analysis tool which was developed to provide 

a capability to the U.S. Nuclear Regulatory Commission and the Center for Nuclear Waste 

Regulatory Analyses (CNWRA) staffs to conduct an independent analysis and review of the 

DOE preclosure safety analysis for a proposed repository at Yucca Mountain, Nevada.

Freitas, C.J., R.B. Codell, and N.A. Eisenberg. 06/10/1994. “SEISMO Version 1.0—A 

Module for Simulation of Seismo-Mechanical Scenarios, Model Description, and User Guide–

IPA 2.” CNWRA 94-008. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

June 1994. 

20.05702.723, Q199406140003, ML033650215 
3-2 

Freitas, C.J., N.A. Eisenberg, and R.G. Baca. 02/25/1994. “DRILLO Code: A Module for 

Simulation of Human Intrusion Scenarios, Model Description, and User Guide, IPA Phase 2.” 

CNWRA 94-005. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

February 1994. 

20.05702.723.415, Q199403160033, ML033630426 

Ghosh, A., R.D. Manteufel, and G.L. Stirewalt. 01/29/1997. “Faulting Version 1.0—A Code 

for Simulation of Direct Fault Disruption, Technical Description and User's Guide.” 

CNWRA 97-002. San Antonio, Texas: Center of Nuclear Waste Regulatory Analyses. 

January 1997. 

20.05708.762.700, Q199704250022, ML040160867 

Gute, G.D., G. Ofoegbu, F. Thomassy, S.-M. Hsiung, G. Adams, A. Ghosh, B. Dasgupta, 

A.H. Chowdhury, and S. Mohanty. 04/30/2003. “Mechfail: A Total-System Performance 

Assessment Code Module for Evaluating Engineered Barrier Performance Under Mechanical 

Loading Conditions.” CNWRA 2003-06. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. May 2003. 

20.06002.01.101.340, Q200305010001, ML040350587 

Hofmann, R.B. and J.H. Bangs. 05/01/1993. “SEISM 1 Code: Adaptations for Use in the 

Western U.S.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

May 1993. 

20.05702.003, Q199305210004. ML040200348 

Janetzke, R.W. and B. Sagar. 05/01/1991. “RDFREE: A Fortran Utility for Format Free 

Input—User's Guide.” CNWRA 91-005. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. June 1991. 

20.03702.065, Q199107160022, ML040210568 

Janetzke, R.W. and B. Sagar. 04/01/1991. “preFOR: A Pre-Processor for Fortran Files User's 

Manual.” CNWRA 91-003. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. April 1991. 

20.03704.065, Q199107160020, ML040210564 

Janetzke, R.W., T.Y. Tony, and P.C. Lichtner. 09/07/1994. “SMLEXC: A Small Executive 

Code for Substantially Complete Containment Example Analysis of a Reference Container.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 1994. 

20.05702.551, Q199409140002, ML033650258 

Jarzemba, M.S., P.A. LaPlante, and K.J. Poor. 06/24/1997. “Ashplume Version 1.0—A Code 

for Contaminated Ash Dispersal and Deposition—Technical Description and User's Guide.” 

Rev. 1.” CNWRA 97-004. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. February 1997 (Revised June 1997). 

20.05708.762, Q199709240003, ML040200069 

Leslie, B. and C. Grossman 09/25/2007. “Total-System Performance Assessment (TPA) 

Version 5.1 Code Module Descriptions and User Guide.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. September 2007. 20.06002.01.354.720, Q200709250003, 

ML072710060 TPA Version 5.1 is a review tool prepared with CNWRA staff input developed to 

assist in prelicensing activities and reviewing a potential U.S. Department of Energy (DOE) 

license application. 
3-3 

Lichtner, P.C. and M.S. Seth. 09/19/1996. “User's Manual for MULTIFLO: Part II: MULTIFLO 

1.0 and GEM 1.0 Multicomponent-Multiphase Reactive Transport Model.” CNWRA 96-010. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 1996. 

20.05708.562.631, Q199704250003, ML040160828 

Lichtner, P.C., J. Song, T.Y. Torng, and J.C. Walton. 01/30/1995. “SCCEX: A Computer 

Code for Substantially Complete Containment Example Analysis of a Reference Container 

Version 1.01.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

January 1995. 

20.05702.551, Q199502020001, ML040160707 

Lozano, A.S., H. Karimi, J.P. Cornelius, R.D. Manteufel, and R.W. Janetzke. 07/28/1994. 

“INVENT: A Module for the Calculation of Radionuclide Inventories, Software Description and 

User Guide.” CNWRA 94-016. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. July 1994. 

20.05702.723, Q199408030001, ML033650226 

Maxwell, T., B. Dasgupta, G. Adams, R. Benke, and N. Eisenberg. 01/01/2005. “Preclosure 

Safety Analysis (PCSA) Tool Version 3.0 (User Guide).” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. January 2005. 

20.06002.01.334, Q200501120005, ML050700283 

Mohanty, S., G.A. Cragnolino, T. Ahn, D.S. Dunn, P.C. Lichtner, R.D. Manteufel, and 

N. Sridhar. 09/01/1996. “Engineered Barrier System Performance Assessment Code: 

EBSPAC Version 1.0 B—Technical Description and User's Manual.” CNWRA 96-011. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 1996. 

20.05708.572.640, Q199704100015, ML040160812 

O'Campo, A. and R.W. Janetzke. 04/12/1994. “AIRCOM: A Module for Iterative Performance 

Assessment Phase 2.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

April 1994. 

20.05702.723, Q199404150004, ML033630618 

Painter, S. and M.S. Seth. 08/19/2003. “MULTIFLO User's Manual MULTIFLO Two-Phase 

Nonisothermal Coupled Thermal-Hydrologic-Chemical Flow Simulator.” Version 2.0, Rev 0, 

Change 0. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 2003. 

20.06002.01.072.320, Q200308250008, ML033640210 

Sagar, B. and R. Janetzke. 08/20/1993. “Total-System Performance Assessment (TPA) 

Computer Code: Description of Executive Module, Version 2.0.” CNWRA 93-017. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 1993. 

20.05702.065.145.000, Q199309200007, ML033630420 

Sagar, B. and R.W. Janetzke. 07/16/1991. “Total System Assessment Computer Code: 

Description of Executive Module.” CNWRA 91-009. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. July 1991. 

20.03702.065, Q199107190028, ML040230527 

 
3-4 

Sagar, B. and A.K. Runchal. 02/13/1992. “PORFLOW: A Multifluid Multiphase Model for 

Simulating Flow, Heat Transfer, and Mass Transport in Fractured Porous Media User's 

Manual—Version 2.40.” CNWRA 92-003. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. February 1992. 

20.03704.112, Q199202270002, ML040220612 

Also published later in 1992 as NUREG/CR-5991. 

Sagar, B., R.B. Codell, J. Walton, and R.W. Janetzke. 07/30/1992. “SOTEC: A Source 

Term Code for High Level Nuclear Waste Geologic Repositories.” CNWRA 92-009. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. July 1992. 

20.03702.065, Q199208120003, ML033640032 

Seth, M.S. and P.C. Lichtner. 05/01/1996. “User's Manual for MULTIFLO: Part 1. 

Metra 1.0 B Two-Phase Nonisothermal Flow Simulator.” CNWRA 96-005. San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. May 1996. 

20.05708.562, Q199607160005, ML040230606 

Stothoff, S.A. 09/01/1994 “BREATH Version 1.0–Coupled Flow and Energy Transport in 

Porous Media, Simulator Description and User Guide.” CNWRA 94-020. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. September 1994. 

20.05704.192, Q200401130007, ML040780274 

The BREATH computer code is designed to simulate one-dimensional flow of a liquid 

phase and dispersive transport of the corresponding vapor species, coupled with energy 

transfer, in a heterogeneous porous medium. 

Stothoff, S.A. 05/23/1995. NUREG/CR–6333, “BREATH Version 1.1–Coupled Flow and 

Energy Transport in Porous Media, Simulator Description and User Guide: San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. May 1995. 

20.05704.192, Q199506080001 

(This report is publicly available at http://www.osti.gov/bridge/servlets/purl/204666-

s85Ob5/webviewable/204666.pdf). Also published as CNWRA 94-020.Torng, T.Y., 

P.C. Lichtner, and J.C. Walton. 07/14/1994. “SCCEX: A Computer Code for Substantially 

Complete Containment Example Analysis of a Reference Container.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. July 1994. 

20.05702.551, Q199408030002, ML033650230 

Walton, J.C. and S. Kalandros. 08/27/1992. “MARIANA—A Simple Chemical Equilibrium 

Module, Version 1.0.” CNWRA 92-020. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. August 1992. 

20.03702.231, Q199209100004, ML033640065 

Walton, J.C. and S.K. Kalandros. 08/01/1992. “TWITCH—A Model for Transient Diffusion, 

Electromigration, and Chemical Reaction in One Dimension, Version 1.0.” CNWRA 92-019. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 1992. 

20.03702.231, Q199209140003, ML033640116 
4-1 

4 PRECLOSURE OPERATIONS AND SAFETY 

Adams, G. 09/28/2011. “Quantifying Low Probability Human Failure Events.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.128, Q201109290001 

Gonzalez, S.H., J.A. Stamatakos, K.R. Murphy, and H.L. McKague. 06/28/2004. 

“Preliminary Evaluation and Analyses of the U.S. Department of Energy Geotechnical Data for 

the Waste Handling Building Site at the Potential Yucca Mountain Repository.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. June 2004. 

20.06002.01.102.442, Q200406290004, ML083510555 

Hageman, J.P. and R. Weiner. “Transportation of Radioactive Materials.” Technology Today. 

pp. 16–19. San Antonio, Texas: Southwest Research Institute. March 1992. 

Karimi, H., M.S. Jarzemba, H.K. Manaktala, A.H. Chowdhury, and M.P. Ahola. 06/23/1995. 

“Compliance Determination Computer Codes for Preclosure Safety Assessments.” 

CNWRA 95-011. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

June 1995. 

20.05704.623, Q199506260005, ML040210657 

This report identifies the capabilities of five sets of commercially available computer 

codes, based on reported information, that could be used to support a safety review to 

determine the adequacy of the U.S. Department of Energy compliance demonstration of 

preclosure regulatory requirements. These requirements are relevant to radiation shielding 

evaluation, underground ventilation calculation, radiation dose assessment, criticality 

calculation, and structural and mechanical analysis. 

Lesher, M., A. Ghosh, and B. Dasgupta. 08/21/2003. “Assessment of Subsurface 

Transporter System for the Proposed Repository at Yucca Mountain.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. August 2003. 

20.06002.01.102.350, Q200308250009, ML040350694 

Povetko, O.G. “An Analysis of External Radiation Dose Fields in an Underground Facility at the 

Potential HLW Geologic Repository at Yucca Mountain, Nevada.” Nuclear Technology.

Vol. 163, No. 1. pp. 31-37. 2008. 

Weiner, R.F., P.A. LaPlante, and J.P. Hageman. “An Approach to Assessing the Impacts of 

Incident-Free Transportation of Radioactive Materials: Air Transportation.” Risk Analysis. 

Vol. 11, No. 4. pp. 654–660. 1991. 

Annual radiation doses and risks to passengers and crew are calculated for shipments of 

radioactive materials in passenger aircraft under accident-free and incident-free conditions; 

(i.e., under normal transportation conditions). The 1982 database developed by 

Sandia National Laboratories is used, and calculations are made using RADTRAN 4.0. This 

paper is one of two papers estimating radiological risk associated with incident-free 

transportation of radioactive materials. 

Weiner, R.F., P.A. LaPlante, and J.P. Hageman. “An Approach to Assessing the Impacts of 

Incident-Free Transportation of Radioactive Materials: Highway Transportation.” Risk Analysis. 

Vol. 11, No. 4. pp. 661–666. 1991. 
5-1 

5 POSTCLOSURE PERFORMANCE ASSESSMENT AND MODEL 

DEVELOPMENT 

Ababou, R., R.C. Bagtzoglou, and E.F. Wood. “On the Condition Number of Covariance 

Matrices in Kriging, Estimation, and Simulation of Random Fields.” Mathematical Geology. 

Vol. 26, No. 1. pp. 99–133. 1994. 

Baca, R.G., and M.S. Jarzemba. 08/08/1997. “Detailed Review of Selected Aspects of Total 

System Performance Assessment 1995.” Revised. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. August 1997. 

20.05708.761, Q199708130001, ML040200160 

Benke, R.R. 12/02/2003. “Analytical and Numerical Solutions of the Expected Number of 

Occurrences for Combinations of Events Sequences Due to Variability.” Applied Mathematics 

and Computation. Vol. 190, No. 2. pp. 1824–1838. 2007. 

Bonano, E.J. and R.G. Baca. 02/01/1994. “Review of Scenario Selection Approaches for 

Performance Assessment of High-Level Waste Repositories and Related Issues.” 

CNWRA 94-002. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

February 1994. 

20.05704.191.094.002, Q199403160036, ML033640272 

DeWispelare, A.R., L.T. Herren, and R.T. Clemen. 06/17/1994. “The Use of Probability 

Elicitation for High-Level Nuclear Waste Regulation Program.” International Journal of 

Forecasting. Vol. 11, No. 1. pp. 5–24. 1995. 

Green, R.T., G.W. Wittmeyer, M.A. Muller, A.C. Bagtzoglou, and E. King. 08/24/1994. 

“Assessment of a Post-Waste Emplacement Geologic Setting Performance Measure.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 1994. 

20.05702.451, Q199409090010, ML033650253 

Separate analyses were conducted for a hypothetical deep geologic repository in a 

fractured, granitic batholith and for a hypothetical deep geologic repository in a variably 

saturated, homogenous tuff unit underlain by a highly permeable, saturated carbonate unit. 

Each analysis was tailored to address different aspects of the proposed post-waste 

emplacement rule. The analyses performed for the granite test case are focused on the 

concept of 'fastest path,' and the analyses conducted for the variably saturated tuff test 

case are focused on the added computational difficulty posed by implementing a 

'post-waste-emplacement' measure in the unsaturated zone. 

Jarzemba, M.S. and F.J. Firth. 10/24/1996. “Background Information and Recommendations 

for a Stylized Human Intrusion Calculation at Yucca Mountain.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. 1996. 

20.05708.761.631, Q199704250012, ML040160846 

This unpublished journal paper is part of an initial study to provide background 

information to aid in the selection of a stylized human intrusion scenario as suggested by the 

National Academy of Sciences. It contains a literature survey that was performed to determine 

the key parameters describing a representative borehole for the scenario. The paper also 

describes a rudimentary calculation to determine the amount of water that may enter the 

described representative borehole. 
5-2 

Jarzemba, M.S. and D.A. Pickett. 05/25/1995. “An Evaluation of the Important Radionuclides 

for Performance Assessment.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. May 1995. 

20.05702.723, Q199505290001, ML040220231 

Lu, Y. and S. Mohanty. “Sensitivity Analysis of a Complex, Proposed Geologic Waste Disposal 

System Using the Fourier Amplitude Sensitivity Test Method.” Reliability Engineering and 

System Safety. Vol. 72, No. 3. pp.275–291. 2001. 

Manteufel, R.D. 09/21/1995. “Application of a Variance-Based Sensitivity Analysis to a 

Complex Computer Program.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. 1995. 

20.05704.192, Q199510110012, ML040780175 

 Unpublished journal manuscript, prepared for Risk Analysis. 

McKague, H.L. and J.A. Stamatakos. 09/29/1997. “Geologic Input for Unsaturated Zone for 

Total Performance Assessment Code Version 3.1. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. September 1997. 

20.05708.471.711, Q199710300012, ML040200096 

Mohanty, S. and R. B. Codell. “Independent Postclosure Performance Estimates of the 

Proposed Repository at Yucca Mountain.” Nuclear Technology. Vol. 148, No 2. pp 105–114. 

2004. 

Mohanty, S. and R.B. Codell. “Sensitivity Analysis Methods for Identifying Influential 

Parameters in a Problem with a Large Number of Random Variables.” C. Brebbia, editor. 

Risk Analysis III. Southampton, United Kingdom: Wessex Institute of Technology Press. 

pp.364–374. 2002. 

Mohanty, S. and R. Codell, “A Performance Assessment Review Tool for the Proposed 

Radioactive Waste Repository at Yucca Mountain, Nevada, USA.” PSAM 5-Probabilistic Safety 

Assessment and Management. S. Kondo and K. Furuta, editors, Frontiers Science Series 34,

Universal Academy Press, Inc.. Tokyo, Japan. Vol. 3. pp. 1,485–1,493. 2000. 

Mohanty, S., and R.B. Codell. 05/16/2003. “Ramifications of Risk Measures in Implementing 

Quantitative Performance Assessment for the Proposed Radioactive Waste Repository at 

Yucca Mountain, Nevada, USA.” Risk Analysis. Vol. 24, No. 3. pp. 537–546. 2004. 

Mohanty, S. and B. Sagar. “Perspectives Paper: Importance of Transparency and Traceability 

in Building a Safety Case for High-Level Nuclear Waste Repositories.” Risk Analysis. Vol. 22, 

No. 1. pp. 7–15. 2002. 

Mohanty, S. and Y-T. Wu. “CDF Sensitivity Analysis Technique for Ranking Influential 

Parameters in the Performance Assessment of the Proposed High-Level Waste Repository at 

Yucca Mountain, Nevada.” Reliability Engineering and System Safety. Vol. 73, No. 2. 

pp 167–176. 2001. 

Mohanty, S. and Y-T. Wu. “CDF Sensitivity Analysis Technique for Ranking Influential 

Parameters in the Performance Assessment of the Proposed High-Level Waste Repository at 

Yucca Mountain, Nevada, USA.” Foresight and Precaution. Vol. 1. M.P. Cottam, D.W. Harvey, 

R.P. Pape, J. Tait (eds.). A.A. Balkema, Rotterdam. The Netherlands. May 2000. 
5-3 

Mohanty, S., R. Benke, R. Codell, K. Compton, D. Esh, D. Gute, L. Howard, T. McCartin, 

O. Pensado, M. Smith, G. Adams, T. Ahn, P. Bertetti, L. Browning, G. Cragnolino, D. 

Dunn, R. Fedors, B. Hill, D. Hooper, P. LaPlante, B. Leslie, R. Nes, G. Ofoegbu, R. 

Pabalan, R. Rice, J. Rubenstone, J. Trapp, B. Winfrey, and L. Yang. 05/19/2005. “Risk 

Analysis for Risk Insights Progress Report.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. May 2005. 

20.06002.01.352, Q200505230001, ML051580323 

The report documents 12 analyses that were conducted to enhance the staff 

understanding of features, events, and processes and associated uncertainties as identified in 

the Risk Insights Baseline Report. The specific areas identified for analysis included repository 

near-field environment, extrusive volcanism, radionuclide transport in the saturated zone, and 

radionuclide inventory. 

Mohanty, S., R. Codell, J.M. Menchaca, R. Janetzke, M. Smith, P. LaPlante, M. Rahimi, and 

A. Lozano. 03/01/2004. Revision 2: “System-Level Performance Assessment of the Proposed 

Repository at Yucca Mountain Using the TPA Version 4.1 Code. Revised. CNWRA 2002-05. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. March 2004. 

20.06002.01.112, Q200501100009, ML041350316 

Mohanty, S., R. Codell, Y.-T. Wu, O. Pensado, O. Osidele, D. Esh, T. Ghosh, and 

T.J. McCartin. 09/28/2011. “History and Value of Uncertainty and Sensitivity Analyses at the 

Nuclear Regulatory Commission and Center for Nuclear Waste Regulatory Analyses.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.170, Q201109280006 

 

Park, J.R., R.G. Baca, N.A. Eisenberg, R.W. Janetzke, and B. Sagar. 02/03/1994. “Iterative 

Performance Assessment (IPA) Phase 2 Total System Code and Scenario Analysis.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 1994. 

20.05702.723, Q199404150003, ML061510399 

Pensado, O., P. LaPlante, D. Pickett, O. Povetko, and L. Howard. 11/13/2002. “Evaluation 

of GoldSim Implementation of Total System Performance Assessment-Site RecommendationCenter for Nuclear Waste Regulatory Analyses (CNWRA) Input.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. November 2002. 

20.06002.112.300, Q200211150001, ML033640105 

This report examines the consistency between the U.S. Department of Energy (DOE) 

TSPA-GoldSim code and the supporting documentation for particular submodels of the code. 

This report summarizes only review activities by the CNWRA staff. 

Sridhar, N. 09/24/1992. “Selection and Evaluation of Models for Substantially Complete 

Containment Example Problem. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. September 1992. 

20.03704.041, Q199209280007, ML033650044 

This report evaluates models for corrosion potential; pit initiation, growth and 

repassivation; crevice corrosion initiation, growth and repassivation; stress corrosion cracking; 

buckling; and fast fracture. Simple parametric equations for the critical potentials associated 

with these phenomena are suggested. 

 
5-4 

Stirewalt, G.L, B.E. Hill, C.B. Connor, and C. Lin. 01/13/1995. “A Critical Review of Data in 

the Center for Nuclear Waste Regulatory Analyses (CNWRA) Volcanism Geographic 

Information System (GIS) Database.” CNWRA 95-003. San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. 1995. 

20.05704.123, Q199501190001, ML040160675 

Stirewalt, G.L., S.M. McDuffie, R.D. Manteufel, and R.W. Janetzke. 06/15/1995. “Technical 

Specifications for a Fault Displacement Module.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. June 1995. 

20.05702.723, Q199506260004, ML040210650 

Walton, J.C., P.K. Nair, and T. Torng. 02/11/1993. “Calculational Approach for Substantially 

Complete Containment Example Problem.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. February 1993. 

20.05707.012, Q199302160002, ML040200248 

This report describes an approach for calculation of waste package lifetime related to the 

"Substantially Complete Containment" requirement in 10 CFR 60. 

Weldy, J.R. 06/12/1997. “Comparison of Reference Input Parameter Values for the Total 

System Performance Assessment of the Proposed Yucca Mountain Repository.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. 1997. 

20.05708.761, Q199708130004, ML040200168 

Weldy, J. and J. Peckenpaugh. 02/26/2003. “Response to the External Peer Review of the 

Total-System Performance Assessment Version 3.2 Code.” CNWRA 2001-002. Rev. 1. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses: September 2001 

(REVISED February 2003). 

20.06002.01.111, Q200303120003, ML031681060 

This report documents the responses of CNWRA and NRC staff to comments from an 

independent peer review panel of eight scientists and engineers with expertise in materials 

science, volcanology, hydrology, rock mechanics, geochemistry, radiation health physics, 

scenario analysis, and performance assessment. The peer review examined the performance 

assessment methodology in the Total-system Performance Assessment (TPA) Version 3.2 

code. This report also describes modifications to the TPA code that have been made 

subsequently or that are under consideration for future versions of the code. 

Wilt, T., A. Chowdhury, and P.A. Cox. 09/23/2011. “Response of Reinforced Concrete 

Structures to Aircraft Crash Impact.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. September 2011. 

20.14002.01.441.158, Q201109260002, ML112690136 

Winkler, R.L. S.C. Hora, and R.G. Baca. 09/18/1992. “The Quality of Expert Probabilities 

Obtained Through Formal Elicitation Techniques.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. September 1992. 

20.03702.062, Q199209240008, ML033650029 

This report focuses on the issue of the quality of experts’ probability estimates as 

obtained through a formalized elicitation process. A broad survey of the scientific literature was 

performed to examine studies where expert judgment was compared with actual data.” 
6-1 

6 SITE CHARACTERIZATION 

These publications describe field and literature studies, at Yucca Mountain and elsewhere, and 

methods and databases used to obtain site information. 

Basse, B. 08/03/1990. “Water Resources in Southern Nevada.” San Antonio, Texas: Center 

for Nuclear Waste Regulatory Analyses. August 1990. 

20.03702.002.305.604, Q199107170012, ML003755474 

A review of available information on long-term projections of regional groundwater needs 

in southern Nevada. The report reviews water resources in southern Nevada and the current 

and projected water demands on these resources.

Bertetti, F.P., and J.D. Prikryl. 07/23/2003. “Mineralogy and Geochemistry of Well Cuttings 

from Selected Early Warning Drilling Project Wells in Fortymile Wash.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. July 2003. 

20.06002.01.141.320, Q200307240002, ML040350688 

This is a report that describes detailed studies of the mineralogy and chemistry of 

cuttings from two Nye County Early Warning Drilling Program wells. Wells, NC-EWDP-02D and 

NC-Washburn-1X, which are located in the southern part of Fortymile Wash along the potential 

groundwater flow path from Yucca Mountain. The cuttings were analyzed using semiquantitative 

x-ray diffraction, thin-section petrography, scanning electron microscopy, x-ray fluorescence, 

and inductively coupled plasma mass spectrometry. 

Connor, C.B., R.H. Martin, P.G. Hunka, J.A. Stamatakos, D.B. Henderson, and 

R.V. Klar. 11/22/1995. “Ground Magnetic Survey of the Little Cones, Crater Flat, Nevada.” 

CNWRA 96-002. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

November 1995. 

20.05702.425, Q199602290013, ML040220433. 

The Little Cones survey was conducted to evaluate the utility of ground magnetic data 

for characterizing igneous intrusions and related structures at small-volume basaltic volcanoes 

in the Yucca Mountain region. 

Dinwiddie, C.L. “The Small-Drillhole Minipermeameter Probe for In-Situ Permeability 

Measurement.” Society of Petroleum Engineers SPE Reservoir Evaluation & Engineering. 

Vol. 8, No. 6. pp. 491–501. DOI:10.2118/84595-PA. December 2005. 

This paper presents an innovative technique for measuring permeability in situ. The 

design of a new minipermeameter probe is discussed, as well as the accompanying analytical 

technique, and the size and shape of the instrument's averaging volume. Some data are 

presented from a Bishop Tuff analog to nonwelded units at Yucca Mountain. 

Dinwiddie, C.L., K.K. Bradbury, R.N. McGinnis, R.W. Fedors, and D.A. Ferrill. “Fault Zone 

Deformation Overprints Permeability of Nonwelded Ignimbrite: Chalk Cove Fault, Bishop Tuff, 

Bishop, California.” Vadose Zone Journal. No. 5. pp. 610–627. (May 2006): 

DOI: 10.2136/vzj2005.0062. 

 
6-2 

Dinwiddie, C.L., K.K. Bradbury, R.N. McGinnis, D.A. Ferrill, and R.W. Fedors. 01/02/2007. 

“Lithological, Structural, and Hydrological Characteristics of Reworked Tuffaceous Sedimentary 

Rock and Interbedded Ashfall Deposits Near Bishop, California: Implications for Lateral Flow.” 

(Manuscript prepared for Vadose Zone Journal) 

20.06002.01.262.630, Q200701020016, ML071690539 

The paper describes how lithological, structural, and in-situ gas permeability data were 

collected and used as a natural analog for nonwelded tuffs of the Paintbrush and Calico Hills 

tuffs at Yucca Mountain to examine the hypothesis that these conditions could laterally divert 

downward flow of water in a sequence of poorly consolidated, reworked tuffaceous rock. 

Dinwiddie, C.L., K.K. Bradbury, R.N. McGinnis, and D.E. Stillman. 09/07/2011. 

“Hydrogeologic Heterogeneity of Faulted and Fractured Glass Mountain Bedded Tuffaceous 

Sediments and Ashfall Deposits: The Crucifix Site Near Bishop, California.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.147, Q201109070003, ML112510093 

Dubreuilh, P., D.J. Waiting, C. Cardenas, and K. Overby. 10/13/2008. “Internet-Based 

Interactive Maps and Satellite Images of the Yucca Mountain Area.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. October 2008. 20.14002.01.141.804, 

Q200810130001, ML082880161, 

This report describes an internet-based tool of interactive maps and satellite images of 

the Yucca Mountain area that was developed on a dedicated internet site accessible to the 

public from any location at http://gedinfomaps.swri.org/YMmaps/.

Farrell, D. and S.K. Sandberg. 01/05/2004. “Electrical Resistivity Studies of Fortymile Wash, 

Nye County, Nevada.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

January 2004. 

20.06002.01.131.330, Q200401080005, ML040270033. 

This report provides a summary of direct current electrical resistivity, induced 

polarization, and time-domain electromagnetic studies performed in southern Fortymile Wash 

and neighboring northern Amargosa Valley, Nevada, in 1998 and 1999 by Center for Nuclear 

Waste Regulatory Analyses (CNWRA). For the level of accuracy required for groundwater flow 

models in the Yucca Mountain region and given the shallow groundwater gradients, the errors in 

the inferred elevations of the water table were generally too large to support detailed modeling 

of groundwater flow in the region. 

Farrell, D.A., J. Winterle, W. Illman, and R.W. Fedors. “Review of Porosity Distributions in 

the Yucca Mountain Region.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. 2000. 

20.01402.861.020, Q200004130002, ML043080446 

Green, R.T., K. Meyer, and G. Rice. 10/01/1994. “Hydraulic Characterization of 

Hydrothermally-Altered Nopal Tuff.” CNWRA 94-027. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. December 1994. 

20.05704.191, Q199505080001, ML040220209. 

Hill, B.E., B.W. Leslie, and C.B. Connor. 09/27/1993. “A Review and Analysis of Dating 

Techniques for Neogene and Quaternary Volcanic Rocks.” CNWRA 93-018. San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. September 1993. 

20.05704.123, Q199310140006, ML040200609. 
6-3 

Hooper, D.M., and D. M. Necsoiu. 09/07/2011. “Spectroscopic Analysis of Tephra as a Site 

Characterization Tool.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2011. 

20.14002.01.441.176, Q201109070001,ML112500246. 

A knowledge management report that summarizes the current understanding of the 

physical properties of volcanic tephra and its spectral response in the visible and nearinfrared regions. These relationships support investigations on the extent of tephra 

deposit remobilization and redistribution, resuspension, weathering and erosion rates, and 

grain-size characteristics. 

LaFemina, P.C., C.B. Connor, J.A. Stamatakos, and D.A. Farrell. “Imaging an Active Normal 

Fault in Alluvium by High-Resolution Magnetic and Electromagnetic Surveys.” Environmental & 

Engineering Geoscience. Vol. 8, No. 3. pp. 193–207. 2002. 

Leslie, B.W. 02/11/1994. “An Annotated Analysis of Logic in the 1992 Report, The Origin and 

History of Alteration and Carbonization of the Yucca Mountain Ignimbrites, by J.S. Szymanski.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. February 1994. 

20.05702.442.421.001, Q199403180021, ML033640282 

 This report provides a systematic analysis of the logic used in the 1992 report listed in 

the title, which asserted that field evidence of mineralization in the shallow subsurface, among 

other factors, supported a conclusion that potential upwelling of hydrothermally derived waters 

and auxiliary gas-assisted processes posed a significant safety hazard for a geologic repository 

at Yucca Mountain. The report provides an annotated logical deconstruction of the premises, 

arguments, and logical analysis of the 1992 report. It examines the current geodynamic 

configuration of the Yucca Mountain region; outcrop and rock core features; and geochemical, 

mineralogical, and isotopic evidence. 

McGinnis, R.N., A.P. Morris, D.A. Ferrill and C.L. Dinwiddie. “Deformation Analysis of 

Tuffaceous Sediments in the Volcanic Tableland Near Bishop, California.” Lithosphere, 1. 

pp. 291–304. 2009. DOI: 10.1130/L43.1. 

McKague, L., P.S. Justus, D. Waiting, A. Morris, R. Pabalan, and J. Stamatakos. 

10/01/2009. “Yucca Mountain Region Field Guide.” Rev. 1. San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. October 2009. 

20.14002.01.401, Q200910050007, ML102770339. 

Murphy, W.M. “Problems in the Study of Water-Rock Interactions Related to Geologic Disposal 

of Nuclear Waste at Hanford, Washington, Yucca Mountain, Nevada, and Vienne, France.” 

Bulletin de Liaison de la Societe Francaise de Mineralogie et de Cristallographie. Vol. 11. 

pp. 94–95. 1999. 

Murphy, W.M. and R.T. Pabalan. 03/16/1994. “Geochemical Investigations Related to the 

Yucca Mountain Environment and Potential Nuclear Waste Repository.” CNWRA 94-006. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. April 1994. 

20.05704.014, Q199405030005, ML033630657 

This report presents the final results of the Geochemistry Research Project conducted at 

the CNWRA for the Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory 

Research. The study focused on experimental determinations and theoretical interpretations of 

fundamental thermodynamic and kinetic properties of minerals and reactions that characterize 

geochemical processes at the proposed nuclear waste repository site at Yucca Mountain and 

that could affect the capacity of the site to isolate nuclear waste. Technical results are 
6-4 

presented in three major sections covering (i) cation exchange studies on clinoptilolite, (ii) 

kinetic and solubility studies on analcime and Na-clinoptilolite, and (iii) conceptual and numerical 

geochemical modeling of natural and repository systems. Also published as NUREG/CR–6288. 

Necsoiu, M., D. Hooper, and R. Benke. 08/13/2008. “Summary of the Relationship Between 

Known Tephra Deposits, Tephra Isopachs, and Topography at Lathrop Wells Volcano, Nevada.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 2008. 

20.14002.01.161.803, Q200808150001, ML082280310 

This report correlates a CNWRA topographic analysis of the region surrounding the 

Lathrop Wells Volcano, developed from a digital elevation model, with existing information such 

as tephra-fall deposit thickness from U.S. Department of Energy (DOE) isopach maps and field 

measurements. The analysis was developed to prepare CNWRA and NRC staff for a 

September 2007 Appendix 7 meeting about fluvial redistribution of radionuclides. 

Pabalan, R.T. “Thermodynamics of Ion-exchange Between Clinoptilolite and Aqueous 

Solutions of Na+/K+ and Na+/Ca2+.” Geochimica et Cosmochimica Acta. Vol. 58, No. 21. 

pp. 4,573–4,590. 1994. 

This paper reports the results of ion exchange experiments that were conducted 

between clinoptilolite, which is the predominant zeolite mineral in altered pyroclastic and 

volcaniclastic rocks, and aqueous mixtures of Na+

/K+ and Na+/Ca2+ to provide a thermodynamic 

basis for understanding zeolite-water interactions in geologic systems. The experimental data 

were interpreted using a Margules thermodynamic formulation for zeolite solid solutions, 

coupled with the Pitzer model for aqueous activity coefficients. The isotherm data were used to 

derive equilibrium constants and Gibbs free energies for the ion-exchange reactions. This 

investigation contributed to a better understanding of how zeolites might influence groundwater 

chemistry at Yucca Mountain. 

Painter. S.L. 01/22/2001 “Statistical Characterization of Spatial Variability in Sedimentary 

Rock.” Heterogeneity in the Crust and Upper Mantle: Nature, Scaling and Seismic Properties. 

J.A. Goff and K. Holliger, eds. New York, New York: Kluwer Academic/Plenum Publishers. 

pp. 187–206. 2003. 

20.01402.861/20.01402.471, Q200101290007 

This paper detailed an examination and evaluation of four different statistical methods 

that may be used to represent spatial variability in sedimentary rocks. Results indicated a 

model based on a mixture of two Laplace distributions and a model based on subordination of a 

Gaussian process both outperformed models based on a Levy-stable distribution and a 

generalized Gaussian distribution. 

Pearcy, E.C. and W.M. Murphy. 10/01/1990. “Geochemical Natural Analogs Literature 

Review.” CNWRA 90-008. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. June 1991. 

20.03704.062, Q199107170001, ML040330616 

Pickett, D.A., J. D. Prikryl, B.W. Leslie, and E.C. Pearcy. 09/28/2011. “Radionuclide Mobility 

at the Nopal I Natural Analog.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. September 2011. 

20.14002.01.441.164, Q201109280007 

This knowledge management report summarizes NRC-sponsored Peña Blanca natural 

analog work—centered on the Nopal I uranium ore deposit—with emphasis on understanding 

radionuclide mobility. The report discusses the beginnings of NRC-sponsored Peña Blanca 

work and Nopal I site selection, hydrologic characterization, fracture characterization, uranium 
6-5 

mineralogy, radionuclide mobility studies, and performance assessment applications. The 

report provides references to all available reports and publications, and describes in more detail 

the results of studies that were unpublished and appeared only in posters or presentations.

Prikryl, J.D., D.A. Pickett, and E.C. Pearcy. 12/27/2002. “Natural Analog Studies at the 

Nopal I Uranium Deposit, Peña Blanca District, Chihuahua, Mexico.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. 2002. 

20.06002.01.141, Q200301140015, ML061310294 

This paper, which was prepared as a chapter for the unpublished book Geology and 

Mineralogy of Radioactive Waste Repositories, summarizes results of natural analog studies at 

the Nopal I uranium deposit and their use in support of performance assessment modeling for 

the proposed Yucca Mountain repository. These studies focused on the mechanisms and 

timing of uraninite alteration and secondary uranium mineral formation, controls on groundwater 

and secondary mineral composition, and processes affecting elemental migration. 

Ressler, T.R., J.A. Stamatakos, K.D. Ridgeway, and J. Winterle. 09/28/2000. “Preliminary 

Hydrostratigraphy of the Valley-Fill Aquifer in Fortymile Wash and the Amargosa Desert.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 2000. 

20.01402.471.060, Q200010240001, ML020100101 

This report describes a detailed investigation of outcrops and evaluation of the 

sedimentary architecture and hydraulic properties of the alluvium of Fortymile Wash. The 

outcrop investigations indicated that the alluvium consists of predominantly conglomerate and 

sandstone. Seven diagnostic sedimentary lithofacies were identified based on grain size, 

sedimentary features, and geometry. Laboratory permeability tests of alluvium samples were 

completed to investigate the variation in permeability between the different lithofacies. The 

results of this report were utilized in several subsequent modeling efforts designed to evaluate 

the effects of heterogeneity and scale on flow and transport. 

Ressler, T.R., K.D. Ridgway, J.A. Stamatakos, and J.M. Sharp, Jr. 11/23/2004. “Facies 

Architecture, Hydrostratigraphy, and Aquifer Characterization of Quaternary Alluvium Adjacent 

to Yucca Mountain, Nevada.” 

20.06002.01.291, Q200412270001 ML061700336. 

Unpublished manuscript prepared for Geological Society of America Bulletin. 

Smart, K.J., D.Y. Wyrick, P.S. Landis, and D.J. Waiting. 03/07/2006. “Summary and 

Analysis of Subsurface Fracture Data From the Topopah Spring Tuff Upper Lithophysal, Middle 

Nonlithophysal, Lower Lithophysal, and Lower Nonlithophysal Zones at Yucca Mountain, 

Nevada.” CNWRA 2005-04. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. March 2006. 

20.06002.01.292.510, Q200603230005, ML060660009. 

This report summarizes subsurface fracture data collected by DOE from the Topopah 

Spring Tuff (upper lithophysal through lower nonlithophysal zones) at Yucca Mountain and 

analyzes the data to provide a revised characterization of key fracture characteristics 

(e.g., fracture orientations and spacings). The analyses were undertaken to assist NRC and 

CNWRA staff with technical reviews in the areas of drift degradation, and unsaturated zone flow 

and radionuclide transport. 

 
6-6 

Stamatakos, J., S. Biswas, and M. Silver. 08/15/2007. “Supplemental Evaluation of 

Geophysical Information Used to Detect and Characterize Buried Volcanic Features in the 

Yucca Mountain Region.” Second Revision. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. August 2007. 

20.06002.01.352.760, Q200708160003, ML072290575. 

Stirewalt, G.L., S.R. Young, and K.D. Mahrer. 09/01/1992. “A Review of Pertinent Literature 

on Volcanic-Magmatic and Tectonic History of the Basin and Range.” CNWRA 92-025. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 1992. 

20.03704.121, Q199210050003, ML033650055. 

Stirewalt, G.L., S.R. Young, and A.P. Morris. 06/19/1992. “Use of Balanced 

Two-Dimensional Geological Cross-Sections in Development of Scenarios for Performance 

Assessment Analyses at Yucca Mountain, Nevada. 

20.03702.132, Q199206250003. ML061370259 

This is an unpublished journal manuscript. This document describes computerized 

cross-section balancing that were applied to define a viable geologic framework for geometric 

representation of major faults beneath Yucca Mountain. The derived two-dimensional model 

consists of a linked listric-detachment fault system with the predicted detachment at a depth of 

5.5 to 5.6 km below sea level. 

Waiting, D.J., L. McKague, and D. Sims. 07/30/2007. “Yucca Mountain Stratigraphic and 

Model Unit Correlation Chart.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. July 2007. 

20.06002.01.292.710, Q200707310003, ML072130112. 

Wittmeyer, G., R. Klar, G. Rice, and W. Murphy. 04/28/1995. “The Center for Nuclear Waste 

Regulatory Analyses (CNWRA) Regional Hydrogeology Geographic Information System 

Database.” CNWRA 95-009. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. April 1995. 

20.05704.131, Q199505180007, ML040220222 

This report describes a Geographic Information System (GIS) database for the Research 

Project on Regional Hydrogeologic Processes of the Death Valley Region that was developed to 

facilitate the evaluation of existing conceptual models and the construction of alternative 

conceptual models of the regional flow system. 

Wyrick, D., R. Fedors, K. Smart, R. Lenhard, R. McGinnis, D. Bannon, and C. Manepally. 

09/27/2011. “Field and Laboratory Experiments to Estimate Bulking Factor for a Lithophysal 

Tuff, Fran Ridge, Yucca Mountain, Nevada.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 2011. 

20.14002.01.441.190, Q201109270011, ML112660359 

Zhu, C. and W.M. Murphy. “On Radiocarbon Dating of Ground Water.” Ground Water. 

Vol. 38. pp. 802–804. 2000.
7-1 

7 IGNEOUS ACTIVITY 

Basu, D., N.K. Adams, J.A. Stamatakos, S. Sparks, and A. Woods. 01/10/2007. “Review of 

Two Electric Power Research Institute Technical Reports on the Potential Igneous Processes 

Relevant to the Yucca Mountain Repository.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. January 2007. 

20.06002.01.302.710, Q200701120001, ML070190134 

Basu, D., K. Das, and N. Adams. 09/19/2008. “Simulations of Magma-Waste Package 

Interactions Using Computational Fluid Dynamics.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. September 2008. 

20.14002.01.151.802, Q200809220006, ML082670317 

This summary report, which is specific to the igneous intrusion scenario, explains the 

technical aspects and results of computational analyses conducted to investigate the flow of 

magma into a subsurface tunnel, including obstacles. 

Basu, D., K. Das, and S. Self. 09/23/2011. “Review of Numerical Analyses for Magma 

Dynamics at Yucca Mountain.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. September 2011. 

20.14002.01.441.157, Q201109230009, ML112660492 

A knowledge management report that documents the important technical aspects and 

results of computational analyses carried out to study magma dynamics and the possible 

interaction between a rising basaltic magma and a hypothetical horizontal repository at Yucca 

Mountain. 

Bokhove, O., A.W. Woods, and A. de Boer. “Magma Flow Through Elastic-Walled Dikes.” 

Theoretical and Computational Fluid Dynamics. Vol. 22. pp. 261–286. 2005. 

The article describes a first-order numerical model to evaluate the likely relationships 

between wall-rock stress and magma flow processes. The numerical model is developed 

using convective-diffusive flow relationships, which are coupled to elastic wall-rock responses 

to stress.

Condit, C.D. and C.B. Connor. 06/30/1995. “Recurrence Rates of Volcanism in Basaltic 

Volcanic Fields: An Example from the Springerville Volcanic Field, Arizona.” Geological 

Society of America Bulletin. Vol. 108. pp. 1,225–1,241. 1996. 

Connor, C.B. and F.M. Conway. “Basaltic Volcanic Fields.” Encyclopedia of Volcanology, 

Academic Press. pp. 331–343. 2000. 

Connor, C.B. and B.E. Hill. “Three Nonhomogenous Poisson Models for the Probability of 

Basaltic Volcanism: Application to the Yucca Mountain Region, Nevada.” Journal of 

Geophysical Research. Vol. 100, B6. pp. 10,107–10,125. 1995. 

Connor, C.B., and B.E. Hill. 06/29/1994. “Strategy for the Evaluation and Use of Probability 

Models for Volcanic Disruptive Scenarios.” CNWRA 94-015. San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. June 1994. 

20.05702.425, Q199407050004, ML040160535 

 
7-2 

Connor, C.B. and C.O. Sanders. 06/23/1994. “Geophysics Review Topical Report: 

Application of Seismic Tomographic and Magnetic Methods to Issues in Basaltic Volcanism.” 

CNWRA 94-013. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. June 

1994. 20.0571998 04.145, Q199406280011 ML040160528 

Connor, C.B., B. Hill, P. La Femina, M. Navarro, and M. Conway. “Soil 222Rn Pulse During 

the June 1995 Phreatic Eruption of Cerro Negro, Nicaragua.” Journal of Volcanological and 

Geothermal Research. Vol. 73. pp. 119–127. 1996. 

 This paper documented post-eruption soil–gas surveys that were conducted to 

determine the extent of shallow degassing. 

Connor, C.B., B.E. Hill, B. Winfrey, N. Franklin, and P.C. LaFemina. “Estimation of Volcanic 

Hazards from Tephra Fallout.” Natural Hazards Review. Vol. 2, No. 1. pp. 33–42. 2001. 

C.B. Connor, P.C. Lichtner, F.M. Conway, B.E. Hill, A.A. Ovsyannikov, I. Federchenko, 

Y. Doubik, V.N. Shapar, and Y.A. Taran. “Cooling of an Igneous Dike 20 Years After 

Intrusion.” Geology. Vol. 25. pp. 711–714. 1997. 

This article documents a modeling study of the cooling rates of a shallow volcanic dike 

emplaced during the 1975 Talbachik eruption in Russia, illustrating how rock thermophysical 

properties and water in the unsaturated zone influenced the cooling rates.

Connor, C.B., S.B.L. Magsino, J.A. Stamatakos, R.H. Martin, P. LaFemina, B.E. Hill, 

S. Lieber. “Magnetic Surveys Help Reassess Volcanic Hazards at Yucca Mountain.” EOS, 

Transactions of the AGU. Vol. 78. pp. 73–78. 1997. 

Connor, C.B., J.A. Stamatakos, D.A. Ferrill, B.E. Hill, G.O. Ofoegbu, M.F. Conway, 

B. Sagar, and J. Trapp. “Geologic Factors Controlling Patterns of Small-Volume Basaltic 

Volcanism: Application to a Volcanic Hazard Assessment at Yucca Mountain, Nevada.” 

Journal of Geophysical Research. Vol. 105. pp. 417–432. 2000. 

Conway, F.M., C.B. Connor, B.E. Hill, C.D. Condit, K. Mullaney, and C.M. Hall. “Recurrence 

Rates of Basaltic Volcanism in SP Cluster, San Francisco Volcanic Field, Arizona.” Geology. 

Vol. 26. pp. 655–658. 1998.

Conway, F.M., D.A. Ferrill, C.H. Hall, A.P. Morris, J.A. Stamatakos, C. Connor, 

A.N. Halliday, and C. Condit. “Timing of Basaltic Volcanism Along the Mesa Butte Fault in the 

San Francisco Volcanic Field, Arizona From 40Ar/39Ar Ages: Implications for Longevity of Cinder 

Cone Alignments.” Journal of Geophysical Research. Vol. 102. pp. 815–824. 1997. 

Doubik, Y.P. and B.E. Hill. “Magmatic and Hydromagmatic Conduit Development During the 

1975 Tolbachik Eruption, Kamchatka, with Implications for Hazards Assessment at Yucca 

Mountain, Nevada.” Journal of Volcanology and Geothermal Research. Vol. 91. pp. 43–64. 

1999. 

Ferrill, D.A, C.B. Connor, J.A. Stamatakos, H.L. McKague, B.E. Hill, G.I. Ofoegbu, and 

R. Terhune. 09/18/1997. “Modeling Fault-Dike Interaction: Implications for Lateral Diversion 

Dikes and Alignment of Volcanos in the Yucca Mountain (Nevada) Region.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. 1997. 

20.05708.471.760, Q199709300004, ML040200083 

This paper uses a summary of a diverse set of analyses for fault and dike interaction to 

illustrate and describe the control of magma ascent by faults. Included are discussions of the 
7-3 

geologic record of fault-dike interaction at Yucca Mountain, theoretical constraints on fault-dike 

interaction, analog modeling results, numerical modeling results, in situ stress controls, and 

volcano cone alignment. 

Hill, B. 11/06/1996. “Constraints on the Potential Subsurface Area of Disruption Associated 

with Yucca Mountain Region Basaltic Volcanos.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. November 1997. 

20.05708.461.701, Q199704250016, ML040160855 

This report summarizes results of Center for Nuclear Waste Regulatory Analyses 

(CNWRA) research at Tolbachik volcano in Kamchatka, Russia, where the process of 

subsurface disruption was well documented during the 1975 eruption. 

Hill, B.E. 03/01/1995. “Expert‐Panel Review of CNWRA Volcanism Research Programs.” 

(Revised). CNWRA 95‐002. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. January 1995. 

20.05704.123.050, Q200605080002, ML040160679 

This document provides a useful example of how to implement an independent 

peer review. 

Hill, B.E., C.B. Connor, M.S. Jarzemba, P.C. LaFemina, M. Navarro, and W. Strauch. “1995 

Eruptions of Cerro Negro Volcano, Nicaragua, and Risk Assessment for Future Eruptions.” 

Geological Society of America Bulletin. Vol. 10. pp. 1,231–1,241. 1998. 

20.05708.461.760, Q199709030007 

Jarzemba, M.S. “Stochastic Radionuclide Distribution After a Basaltic Eruption for Performance 

Assessment of Yucca Mountain.” Nuclear Technology. Vol. 118, No. 2. pp.132–141. 1997. 

This paper describes the initial model for post-eruption dose calculations.

La Femina, P.C., C.B. Connor, B.E. Hill, W. Strauch, and J. Armando Saballos. 

“Magma-Tectonic Interactions in Nicaragua: The 1999 Seismic Swarm and Eruption of Cerro 

Negro Volcano.” Journal of Volcanology and Geothermal Research. Vol. 137 Nos. 1–3. 

pp. 187–199. DOI:10.1016/j.volgeores.2004.05.006. 2004. 

20.06002.01.051.375, Q200304280001 

The study simulates a 1999 eruption of the Cerro Negro volcano in Nicaragua and 

concludes that the temporal and spatial patterns of earthquake swarms, surface ruptures, and 

the eruption location can be explained by using a model in which an eruption is triggered by 

tectonically induced changes in the regional stress field, rather than being initiated by 

magmatic overpressure. 

Magsino, S.L., C.B. Connor, B.E. Hill, J.A. Stamatakos, P.C. La Femina, D.A. Sims, and 

R.H. Martin. 01/27/1998. “CNWRA Ground Magnetic Surveys in the Yucca Mountain Region, 

Nevada (1996–1997).” CNWRA 98-001. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. January 1998. 

20.01402.461.840, Q199803040001, ML032890330 

 This report describes basic methods for identification and characterization of buried 

igneous bodies.

 
7-4 

Menand, T. and J. C. Phillips. “Gas Segregation in Dykes and Sills.” Journal of Volcanology 

and Geothermal Research. Vol. 159, No. 4. pp. 393-408. 2007. 

20.06002.01.302.610, Q200512080007 

This paper investigates 1) how the geometry and connectivity of the plumbing system 

affect the circulation of magma and 2) how this circulation impacts gas segregation. The 

investigation is restricted to the geometry of a vertical conduit connected to a horizontal 

magma body. 

Menand, T., J.C. Phillips, and R.S.J. Sparks. “Circulation of Bubbly Magma and Gas 

Segregation Within Tunnels for the Potential Yucca Mountain Repository.” Bulletin of 

Volcanology. Vol. 70, No. 8. pp. 947–960. 2008. 

This article describes igneous activity analog experiments designed to simulate 

sustained flow of ascending magma and exsolved volatiles from a vertical dike into a 

hypothetical drift at the potential Yucca Mountain repository. These models help bound 

uncertainties in predicting the eruptive style of an actively degassing magmatic system and the 

subsequent effects in the event that basaltic magma was to entrain nuclear waste material.

Phillips, J.C., T. Menand, R.S.J. Sparks, A.J. Hogg, J.A. Stamatakos, and N.K. Adams. 

05/29/2008. “Final Revision of the Steady State Interaction of Rising Magma Within Drifts: 

Summary Report of Magma Flow Dynamics in the Potential Yucca Mountain Repository From 

Experimental Studies Performed at the University of Bristol, Bristol, United Kingdom.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. May 2008. 

20.14002.01.151, Q200805300001, ML081510915 

Stamatakos, J., S. Biswas, and M. Silver. 04/13/2007. “Supplemental Evaluation of 

Geophysical Information Used to Detect and Characterize Buried Volcanic Features in the 

Yucca Mountain Region.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

August 2007. 

20.06002.01.352.760, Q200704160007, ML072290572 and ML072290575 

Stamatakos, J.A., C.B. Connor, and R.H. Martin. “Quaternary Basin Evolution and Basaltic 

Volcanism of Crater Flat, Nevada, from Detailed Ground Magnetic Surveys of the Little Cones.” 

Journal of Geology. Vol. 105. pp. 319–330. 1997. 

Woods, A.W., O. Bokhove, A. de Boer, and B.E. Hill. “Compressible Magma Flow in a 

Two-Dimensional Elastic-Walled Dike.” Earth and Planetary Science Letters. Vol. 246, 

Nos. 3-4. pp. 241–250. 2006. 

Woods, A.W., S. Sparks, O. Bokhove, A-M. LeJeune, C.B. Connor, and B.E. Hill. “Modeling 

Magma–Drift Interaction at the Proposed High-Level Radioactive Waste Repository at 

Yucca Mountain, Nevada, U.S.A.” Geophysical Research Letters. Vol. 29, No. 13. 

pp.19-1–19-4. DOI: 10.1029/2002GL014665. 2002. 

Young, S.R., H.L. McKague, and R.W. Terhune. 10/07/1994. “Influence of Faults on Ascent 

of Mafic Magma by Dike Intrusion.” CNWRA 94-025. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. October 1994. 

20.05702.425, Q199410190001 ML040160563 

This report describes and analyzes a preliminary numerical study of the effects of 

intersection depth and fault dip on the upward transport of magma. 
8-1 

8 STRUCTURAL GEOLOGY AND SEISMICITY 

Bennett, R.A., J.L. Davis, P. Elosegui, B.P. Wernicke, J.K. Snow, M.J. Abolins, 

M.A. House, G.L. Stirewalt, and D.A. Ferrill. 09/18/1997. “Global Positioning System 

constraints on Fault Slip Rates in the Death Valley, Region, California and Nevada.” 

Geophysical Research Letters. Vol. 24. 3,073–3,076. 1997. 

Biswas, S. and J. Stamatakos. 12/14/2007. “Evaluation of the Regional Scale Geologic 

Cross Section Interpretations at Yucca Mountain Based on Modeling of U.S. Department of 

Energy (DOE) Aeromagnetic Anomalies Data.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. December 2007. 

20.06002.01.292.730, Q200712140016, ML073510141 

This report describes modeling analyses obtained using 2004 DOE aeromagnetic data 

to evaluate uncertainties in four existing regional-scale geologic cross section interpretations. 

Connor, C.B., J.A. Stamatakos, D.A. Ferrill, B.E. Hill. “Technical Comment on ‘Anomalous 

Strain Rates in the Yucca Mountain Area, Nevada,’ by Wernicke, et al.” Science. Vol. 282. 

pp. 1007b–1009b. 1998. 

Dunne, W.M., D.A. Ferrill, J.G. Crider, B. Hill, P. La Femina, D. Waiting, A.P. Morris, and 

R. Fedors. 2003. “Orthogonal Jointing During Coeval Igneous Degassing and Normal Faulting, 

Yucca Mountain, Nevada.” Geological Society of America Bulletin. Vol. 115. pp. 1,492–1,509. 

2003. 

Ferrill, D.A. “Critical Re-evaluation of Differential Stress Estimates From Calcite Twins.” 

Tectonophysics. Vol. 285 pp. 77–84. 1998. 

Ferrill, D.A. and A.P. Morris. “Geometric Considerations of Deformation Above Curved 

Normal Faults and Salt Evacuation Surfaces.” The Leading Edge. Vol. 16. pp. 1,129–1,133. 

1997. 

Ferrill, D.A. and A.P. Morris. “Displacement Gradient and Deformation in Normal Fault 

Systems.” Journal of Structural Geology. Vol. 23. pp. 619–638. 2001. 

Ferrill, D.A., A.P. Morris, S.M. Jones, and J.A. Stamatakos. “Extensional Layer-Parallel 

Shear and Normal Faulting.” Journal of Structural Geology. Vol. 20. pp. 355–362. 1998. 

Ferrill, D.A., A.P. Morris, J.A. Stamatakos, D.J. Waiting, R.A. Donelick, and A.E. Blythe. 

09/19/2011. “Fission Track Constraints on Exhumation and Extensional Faulting in Southwest 

Nevada and Eastern California, U.S.A.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 2011. 

20.14002.01.441.145, Q201109190005, ML112630153 

This report presents the entire fission-track data set collected from the Yucca Mountain 

region by the Center for Nuclear Waste Regulatory Analyses since 1993, as well as other 

published data from the region, and provides a summary of results and the constraints provided 

by the data on the timing and rate of lower crustal exhumation in the Yucca Mountain region. 

 
8-2 

Ferrill, D.A., J.A. Stamatakos, S.M. Jones, B. Rahe, H.L. McKague, R.H. Martin, and

A.P. Morris. “Quaternary Slip History of the Bare Mountain Fault (Nevada) from the 

Morphology and Distribution of Alluvial Fan Deposits.” Geology. Vol. 24. pp. 559–562. 1996. 

20.05704.164, Q199603060008 

Ferrill, D.A., J.A. Stamatakos, and H.L. McKague. “Quaternary Slip History of the Bare 

Mountain Fault (Nevada) From the Morphology and Distribution of Alluvial Fan Deposits: 

Reply.” Geology. Vol. 25. p. 190. 1997. 

Ferrill, D., J. Stamatakos, A.P. Morris, R.A. Donelick, A.E. Blythe, S.M. Jones, and 

K. Spivey. 07/14/1997. “Geometric, Thermal, and Temporal Constraints on the Tectonic 

Evolution of Bare Mountain, Nevada.” 

20.05708.471.731, Q199709030009, ML061070270 

Unpublished manuscript prepared for Geological Society of America Bulletin 

Ferrill, D.A., J.A. Stamatakos, and D.W. Sims. “Normal Fault Corrugation: Implications for 

Growth and Seismicity of Active Normal Faults.” Journal of Structural Geology. Vol. 21. 

pp. 1,027–1,038. 1999. 

Ferrill, D.A., G.L. Stirewalt, D. Brent Henderson, J.A. Stamatakos, A.P. Morris, 

B.P. Wernicke, and K.H. Spivey. 08/25/1995. “Faulting in the Yucca Mountain Region: 

Critical Review and Analyses Tectonic Data from the Central Basin and Range Region. 

CNWRA 95-017. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

August 1995. 

20.05704.167.504, Q199509050028, ML040330873 

Gray, M.B., J.A. Stamatakos, D.A. Ferrill, and M.A. Evans. 2005. “Fault Zone Deformation 

Process in Miocene Tuffs at Yucca Mountain, Nevada.” Journal of Structural Geology. Vol. 27. 

pp. 873–1891. 2005. 

Gonzalez, S.H., A.P. Morris, G.I. Ofoegbu, K.J. Smart, and J.A. Stamatakos. 08/22/2006. 

“Review of Peak Ground Velocities for Seismic Events at Yucca Mountain, Nevada.” Rev. 2 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 2006. 

20.06002.01.352.610, Q200608220001, ML062510008 

This report provides an evaluation of the U.S. Department of Energy (DOE) report “Peak 

Ground Velocities for Seismic Events at Yucca Mountain, Nevada”. This evaluation includes a 

comprehensive review of the technical bases used by the DOE to support the proposed 

bounding value for horizontal peak ground velocity, and a summary of current and ongoing 

research in the field of earthquake mechanics with particular emphasis on current or future 

research that could be used to support or refute the proposed bounding value for horizontal 

peak ground velocity. 

Huyse, L., R. Chen, and J.A. Stamatakos. “Application of Generalized Pareto Distribution to 

Constrain Uncertainty in Low-Probability Peak Ground Accelerations.” Bulletin of the 

Seismological Society of America. Vol. 100. pp 87–101. 2010.

 
8-3 

McKague, H.L. 06/11/1996. “Identification of Type II Faults in the Yucca Mountain Region.” 

(Supplement). San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

June 1996. 

20.05708.471.620, Q200310210002, ML040220060 

This report examined more than 400 faults within 100 km [60 mi] of the proposed Yucca 

Mountain repository site to identify faults as candidates for more detailed investigations. This 

report is a revision of a report that was first transmitted 04/12/1996. Note that some figures, on 

pages 11 through 18, were not included in this version of the report due to technical difficulties 

in retransmitting the images. However, the missing figures can be viewed on pages 11 through 

18 in the April 1996 version of the report (20.05708.471.620, Q199604230008, ML040220033). 

McKague, L., D. Ferril, K. Smart, J. Stamatakos, and D. Waiting. 12/15/2010. “Synthesis 

Report for Yucca Mountain Region Tectonic Models.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. November 2010. 

20.14002.01.441.102, Q201012150001, ML103500198 

This report provides a review of the tectonic models proposed for the Yucca 

Mountain region.

McKague, H.L., J.A. Stamatakos, and D.A Ferrill. 01/30/1997. “Type I Faults in the Yucca 

Mountain Region.” Rev. 1. CNWRA 96-007. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. November 1996. 

20.05708.471, Q200310210003, ML040220051 

Morris, A.P. and D.A. Ferrill. “Constant Thickness Deformation Above Curved Normal Faults.” 

Journal of Structural Geology. Vol. 21. pp. 67–83. 1999. 

Morris, A.P., D.A. Ferrill, and D.B. Henderson. “Slip Tendency Analysis and Fault 

Reactivation.” Geology. Vol. 24. pp. 275–278. 1996. 

Morris, A.P., D.A. Ferrill, D.W. Sims, N. Franklin, D.J. Waiting. “Patterns of Fault 

Displacement and Strain at Yucca Mountain, Nevada.” Journal of Structural Geology. Vol. 26. 

pp.1,707–1,725. 2004. 

Morris, A.P., S.R. Young, and W.L. Stirewalt. 09/29/1992. “Geometric Analysis of Alternative 

Models of Tectonic Faulting at Yucca Mountain.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. September 1992. 

20.03702.132, Q199210050008, ML033650067 

Newman, A.V., T.H. Dixon, G.I. Ofoegbu, and J.E. Dixon. “Geodetic and Seismic Constraints 

on Recent Activity at Long Valley Caldera, California: Evidence for Viscoelastic Rheology.” 

Journal of Volcanology and Geothermal Research. Vol. 105. pp.183–206. February 2001. 

G.I. Ofoegbu and D.A. Ferrill. “Mechanical Analyses of Listric Normal Faulting with Emphasis 

on Seismicity Assessment.” Tectonophysics. Vol. 284. pp. 65–77. 1998. 

Ofoegbu, G.I., D.A. Ferrill, K.J. Smart, and J.A. Stamatakos. 06/22/1998. “Patterns of 

Ground Motion Amplitudes From Numerically Simulated Earthquakes.” 

20.05708.471, Q199807010002, ML003748117, ML003748117 

Unpublished manuscript prepared for the Bulletin of the Seismological Society 

of America. 
8-4 

Rahe, B., D.A. Ferrill, and A.P. Morris. “Physical Analog Modeling of Pull-Apart Basin 

Evolution.” Tectonophysics. Vol. 285. pp. 21–40. 1998. 

The paper documents modeling results that constrain the sequence of structural 

evolution of pull-apart basins and factors controlling their overall model geometry. The results 

provide conceptual constraints for identifying the stage and development of pull-apart basins 

and characterizing earthquakes associated with the controlling strike slip systems. 

Ridgway, K., J. Stamatakos, M. Gutenkunst, and P. Dubreuilh. 07/31/2011. “Stratigraphic 

Analysis and Regional Correlation of Oligocene and Early Miocene Strata in the Yucca 

Mountain Area.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. July 

2011. 

20.14002.01.441.108, Q201108010001, ML112140240 

Sims, D.W., D.A. Ferrill, and J.A Stamatakos. “Role of a Ductile Décollement in the 

Development of Pull-Apart Basins.” Journal of Structural Geology. Vol. 21. pp. 533–554. 

1999. 

Sims, D.W., H.L. McKague, D.J. Waiting, and S.L. Colton. 10/16/2008. “Reconsideration of 

Geomorphic Evidence Regarding the Neotectonic Setting of Fortymile Wash, Nye County, 

Nevada.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. October 2008. 

20.06002.01.292.700, Q200810160001, ML083030516 

Sims, D.W., J.A. Stamatakos, D.A. Ferrill, H.L. McKague, D.A. Farrell, and A. Armstrong. 

12/03/1999. “Three-Dimensional Structural Model of the Amargosa Desert, Version 1.0: Report 

to Accompany Model Transfer to the Nuclear Regulatory Commission.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. December 1999. 

20.01402.471.040, Q199912080003, ML033630387 

The report describes a three-dimensional structural model developed by CNWRA staff to 

analyze groundwater flow in the Amargosa Desert region. It provided the basic regional 

structural framework for abstraction into regional groundwater flow models. As more structural 

data became available, the model was revised and renamed as the Three-Dimensional 

Hydrogeologic Model of the Amargosa Desert (see 20.06002.01.272.621, Q200707060003, 

ML071900243 for Version 2.0). 

Smart, K.J. 02/20/2004. “Examination of Effects of Geologic Features on Thermally Induced 

Stress at Yucca Mountain, Nevada.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. 2004. 

20.06002.01.051.470, Q200402240005, ML041670379 

This report summarizes the assumptions and results of previous DOE thermal stress 

studies and considers how thermal stress distribution potentially may be affected by aspects of 

geology not fully explored in previous DOE work.

Stamatakos, J.A. and D.A. Ferrill. “Strike-Slip Fault System in Amargosa Valley and Yucca 

Mountain, Nevada.” Tectonophysics. Vol. 294. pp. 151–160. 1998. 

Stamatakos, J.A., D.A. Ferrill, and K.A. Spivey. “Paleomagnetic Constraints on the Tectonic 

History of Bare Mountain, Nevada.” Geological Society of America Bulletin. Vol. 110 

pp. 1,530–1,546. 1998. 
8-5 

Stamatakos, J., D.A. Ferrill, and A.P. Morris. 09/15/2011. “Age and Timing of Extensional 

Faulting and Basin Growth at Crater Flat, Nevada.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. September 2011. 

20.14002.01.441.120, Q201109150005, ML112580263 

Waiting, D.L., R. Chen, J.G. Crider, W.M. Dunne, R.W. Fedors, D.A. Ferrill, M.B. Gray, 

B.E. Hill, P.C. La Femina, H.L. McKague, A.P. Morris, D.W. Sims, and J.A. Stamatakos. 

09/21/2001. “Technical Assessment of Structural Deformation and Seismicity at Yucca 

Mountain, Nevada.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2001. 

20.1402.471.120, Q20011004005, ML033630629 

This report provides a summary of tectonic information relevant to understanding effects 

on igneous processes. 

Young, S.R., A.P. Morris, and G.L. Stirewalt. 11/13/1992. “Preliminary Structural 

Interpretation of Reflection Seismic Line AV-1.” CNWRA 92-024. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. November 1992. 

20.05702.003, Q199211180014, ML040200192 

Young, S.R. and G.L. Stirewalt. 09/28/1990. “Evaluation of Computer-Assisted Cross Section 

Balancing Methods of Analysis of Subsurface Fault Geometry in the Vicinity of Yucca Mountain, 

Nevada: A Pilot Study.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

1990. 

20.03702.002, Q199107230004, ML040220081 

This pilot study evaluated the usefulness of computer-assisted geological cross section 

balancing methods in the geometric and kinematic analysis of subsurface structures in the 

vicinity of Yucca Mountain, including underlying listric normal fault and detachment fault 

geometries and their relationships in a linked fault system. 

Young, S.R., G.L. Stirewalt, and A.P. Morris. 10/23/1992. “Geometric Models of Faulting at 

Yucca Mountain.” CNWRA 92-008. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. October 1992. 

20.05702.132, Q199210260004, ML033650105, ML033650108, ML033650111
9-1 

9 CLIMATE AND INFILTRATION 

Ababou, R. 06/12/1990. “High-Resolution Modeling of Strip Source Infiltration: 

Three-Dimensional Synthetic Experiment Analogous to Las Cruces Trench Experiment.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 1990. 

20.03704.051, Q199107160019 ML040210558 

The paper describes how a high-resolution, three-dimensional finite difference model 

(BIGFLO) was used to model strip source infiltration and natural drainage in a randomly 

heterogeneous and imperfectly stratified soil. The flow regime, soil properties, and boundary 

conditions used were similar to those associated with a vadose zone hydrology experiment at 

the Las Cruces Trench Site in southern New Mexico. 

Bagtzoglou, A.C., S.A. Stothoff, and M.A. Muller. 10/30/1995. “Progress Towards 

Estimating Infiltration and Deep Percolation at the Yucca Mountain Site.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. 1995. 

20.05702.723, Q199601050012, ML040220364 

This is a numerical modeling study that used a ten-year sequence of weather data. The 

simulations indicated that alluvial covers with higher values of permeability allow less liquid 

water to percolate in the deeper parts of the rock due to rate-limiting evaporation. Deep 

percolation simulations were conducted to address the effect of spatial and temporal averaging 

of infiltration and to develop an improved probability density function for percolation through the 

proposed repository horizon at two cross sections, including the Solitario Canyon fault area. 

DeWispelare, A.R., L. Tandy Herren, M.P. Miklas, and R.T. Clemen. 08/30/1993. “Expert 

Elicitation of Future Climate in the Yucca Mountain Vicinity—Iterative Performance Assessment 

Phase 2.5.” CNWRA 93-016. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. August 1993. 

20.05702.065.850.001, Q199309140002, ML033630407 

Groeneveld, D.P., R.W. Fedors, and S.A. Stothoff. “Weedy Brome Grasses and Their 

Potential Effect on the Infiltration and Recharge Rates in the Vicinity of Yucca Mountain, 

Nevada.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 1999. 

20.01402.861.985, Q199908260001, ML033630380 

This report includes a brief botanical guide to plant species in the Yucca Mountain 

region.

Stothoff, S. 11/10/2009. “Subsurface Observations Related to Infiltration at Yucca Mountain.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. November 2009. 

20.14002.01.111.860, Q200911100001, ML093160095 

This report summarizes geochemical and thermal information that the U.S. Department 

of Energy (DOE) used to estimate net infiltration and deep percolation fluxes at Yucca 

Mountain. 

Stothoff, S. 08/21/2008. “Infiltration Tabulator for Yucca Mountain: Bases and Confirmation.” 

CNWRA 2008-001. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

August 2008. 

20.14002.01.111.820, Q200808210003, ML082350701 

This report is the third in a series of three reports assessing the role of climate change 

on infiltration at Yucca Mountain. This report describes the Infiltration Tabulator for Yucca 

Mountain (ITYM ), a mathematical model that provides estimates of mean annual infiltration 
9-2 

and that was developed specifically to consider the potential effects of terrain and climate at 

Yucca Mountain, Nevada, under present and potential future conditions. 

Stothoff, S.A. 09/29/2011. “Uncertainty and Variability: Water Flow Through Yucca Mountain 

Over the Next Million Years.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. September 2011. 

20.14002.01.441.130, Q201109290004 

Stothoff, S.A. “Sensitivity of Long-Term Bare-Soil Infiltration Simulations to Hydraulic 

Properties in an Arid Environment.” Water Resources Research. Vol. 33, No. 4. pp. 547–558. 

1997. 

This paper assesses the impact of hydraulic properties in two idealized simulations of 

infiltration through deep colluvium and alluvium to fractured, densely welded tuff. 

Stothoff, S. and M. Musgrove. 11/14/2006. “Literature Review and Analysis: Climate and 

Infiltration.” CNWRA 2007-002. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. November 2006. 

20.06002.01.252.720, Q200611140002, ML063190115 

This report is the first in a series of three reports assessing the role of climate change on 

infiltration at Yucca Mountain. The report documents a review of literature from outside of the 

Yucca Mountain program related to infiltration under climates analogous to climates that may 

occur at Yucca Mountain. 

Stothoff, S. and G. Walter. 09/20/2007. “Long-Term Average Infiltration at Yucca Mountain, 

Nevada: Million-Year Estimates.” CNWRA 2007-003. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. August 2007. 

20.06002.01.252.730, Q200709210002, ML072760607 

This report is the second in a series of three reports assessing the role of climate 

change on infiltration at Yucca Mountain. In this report, the authors constructed potential future 

climate sequences based on orbital mechanics and paleoclimatic inferences, and used an 

infiltration tabulator model to estimate million-year-average net infiltration at Yucca Mountain for 

specified climatic sequences. 

Stothoff, S.A, D. Or, D.P. Groeneveld, and S.B. Jones. 07/29/1997. “The Effect of 

Vegetation on Infiltration in Shallow Soils Underlain by Fissured Bedrock.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. July 1997. 

20.05708.861.730, Q199709300002, ML040200076 

The report describes field and modeling studies that were performed to achieve insight 

into the hydrologic behavior of a semi-arid environment characterized by shallow, permeable 

soils overlying bedrock with soil-filled fissures. Particular attention is given to the impact of 

vegetation on the hydrologic system, including the observation that widely spaced soil-filled 

fissures appear to be conducive to plant growth even when fissures are buried below soils as 

deep as 30 cm. 

Walter, G. 12/09/2005. Revised: “Analysis of Factors Contributing to Uncertainty in Estimating 

Future Climates at Yucca Mountain.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. November 2005. 

20.06002.01.252.531, Q200512090004, ML053470163 

This report summarizes the approach taken by the DOE to estimate the nature and 

sequence of future climate, and discusses the uncertainties that may affect those estimates. 
9-3 

Wittmeyer, G.W., M.P. Miklas, R.V. Klar, D. Williams, and D. Balin. 08/26/1996. “Use of 

Groundwater in the Arid and Semi-Arid Western United States: Implications for Yucca Mountain 

Area.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 1996. 

20.05708.771.640, Q199704250002, ML040160822 

The report summarizes a survey of water well practices in four arid and semi-arid 

southwestern states: Arizona, Nevada, New Mexico, and Texas. Water wells drilled deeper 

than 150 m are tabulated, located, and described by intended use. Wells which provide water 

from more than 240 m depth are discussed individually. Representative costs of typical public 

water supply and agricultural deep wells are presented. 

Woolhiser, D.A., R.W. Fedors, R.E. Smith, and S.A. Stothoff. “Estimating Infiltration in the 

Upper Split Wash Watershed, Yucca Mountain, Nevada.” Journal of Hydrologic Engineering. 

Vol. 11, No. 2. pp. 123-134. 2006. 

The authors used a distributed rainfall-runoff model (KINEROS2) and precipitation 

measurements to estimate the spatial distribution of storm and mean annual infiltration into soils 

and bedrock on hillslopes and channels of a small watershed on Yucca Mountain , Nevada. 

The objective was to examine the impact of the runoff-runon phenomenon on the possible 

spatial focusing of net infiltration.
10-1 

10 EVOLUTION OF THE NEAR-FIELD ENVIRONMENT 

These are reports or papers that focus primarily on coupled processes (thermal, hydrological, 

mechanical, and chemical) that are expected to change over time in the repository near-field. 

Ahola, M. P. 09/27/1995. “Expert-Panel Review of Center for Nuclear Waste Regulatory 

Analyses (CNWRA) Coupled Thermal-Mechanical-Hydrological Processes Research Project.” 

CNWRA 95-021. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 1995. 

20.05704.036, Q199511070005, ML040220346 

An independent panel of five experts reviewed the ongoing research on coupled 

thermal-mechanical-hydrological (TMH) processes at the Center for Nuclear Waste Regulatory 

Analyses (CNWRA). The goals of the review were to (i) critically review the objectives and 

approaches of CNWRA coupled TMH research and its application to licensing issues at the 

proposed Yucca Mountain high-level waste repository site, (ii) recommend improvements to the 

research scope and methodologies, and (iii) investigate new issues that may not be part of the 

original research plans. This report includes the individual summary reports and responses to 

each reviewer's comments and recommendations. 

Ahola, M.P., S.-M. Hsiung, L.J. Lorig, and A.H. Chowdhury. 04/01/1992. 

“Thermo-Hydro-Mechanical Coupled Modeling: Multiple Fracture Model, BMT2; Coupled 

Stress-Flow Model, TC1, DECOVALEX Phase 1.” CNWRA 92-005. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. April 1992. 

20.03704.039, Q199204150012, ML040330769

Ahola, M.P., A. Thoraval, and A.H. Chowdhury. “Distinct Models for the Coupled T-M-H 

Processes: Theory and Implementation.” Chapter 7, Coupled Thermo-Hydro-Mechanical 

Processes of Fractured Media. O. Stephansson, L. Jing, and C-F. Tsang, eds. Developments 

in Engineering, 79. Amsterdam, The Netherlands: Elsevier Science. pp. 181–211. 1996. 

Ahola, M.P., S.-M. Hsiung, and D.D. Kana. “Experimental Study on Dynamic Behavior of 

Rock Joints.” Chapter 18, Coupled Thermo-Hydro-Mechanical Processes of Fractured Media. 

O. Stephansson, L. Jing, and C-F. Tsang, eds. Developments in Engineering, 79. Amsterdam, 

The Netherlands: Elsevier Science. pp. 467–494. 1996. 

Ahola, M.P., L.J. Lorig, A.H. Chowdhury, and S.-M. Hsiung. 08/30/1993. 

“Thermo-Hydro-Mechanical Coupled Modeling: Near Field Repository Model, BMT3.” 

CNWRA 93-002. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 

1993. 20.05704.039.020, Q199311090002, ML040200648 

The report presents results of a distinct element analysis as part of the Phase II activities 

of the international cooperative project DECOVALEX (acronym for the DEvelopment of COupled 

models and their VALidation against EXperiments in nuclear waste isolation). The analysis was 

conducted for the benchmark test problem identified as the Near-Field Repository Model 

(BMT3), using the Universal Distinct Element Code (UDEC). The test problem was designed to 

compare modeling results based on both continuum and discontinuum approaches for 

simulating coupled thermal-hydrological-mechanical (THM) behavior for a near-field repository. 

 
10-2 

Ahola, M.P., S. Mohanty, and A. Makurat. “Coupled Mechanical Shear and Hydraulic Flow 

Behavior of Natural Rock Joints.” Chapter 15, Coupled Thermo-Hydro-Mechanical Processes 

of Fractured Media. O. Stephansson, L. Jing, and C-F. Tsang, eds. Developments in 

Engineering, 79. Amsterdam, The Netherlands: Elsevier Science. pp. 393–423. 1996. 

Ahola, M.P., G.I. Ofoegbu, A.H. Chowdhury, and S.-M. Hsiung. 09/29/1994. 

“Thermo-Hydro-Mechanical Coupled Modeling: Big-Ben Experiment, 

TC3—Decovalex-Phase III.” CNWRA 94-021. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 1994. 

20.05704.039, Q199410140002, ML040230574 

Angell, P., J.A. Apps, G.A. Cragnolino, S.M. Hsiung, P.C. Lichtner, W.M. Murphy, 

P. Pabalan, D.A. Pickett, N. Sridhar, S.A. Stothoff, and D.A. Turner. 06/27/1996. “Evolution 

of the Near-Field Environment in the Proposed High-Level Waste Repository at Yucca 

Mountain—A Review of Hypotheses.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. 1996. 

20.05708.561.620, Q199607160004, ML040230602 

This report presents a review of hypotheses on the evolution of the near-field 

environment, primarily gleaned from the literature. An effort is made to evaluate the set of 

processes and the environmental parameters that may have important impacts on performance. 

Specifically, the report addresses thermal-hydrologic effects, hydrothermal-chemical effects, 

radiolysis effects on radionuclide mobilization, thermal-mechanical effects, cementitious 

materials, corrosion of container materials, waste form alteration products, microbiological 

effects, and near-field transport processes. 

Baca, R.B. and M.S. Seth. 02/27/1996. “Benchmark Testing of Thermohydrologic Computer 

Codes.” CNWRA 96-003. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. February 1996. 

20.05708.661, Q199603220008, ML040220029 

Three major objectives of this benchmark testing study were to (i) compare and contrast 

the simulation capabilities of the U.S. Nuclear Regulatory Commission (NRC)/CNWRA codes 

with those of the U.S. Department of Energy (DOE), (ii) identify and understand any significant 

differences that may arise between DOE and NRC/CNWRA code applications, and (iii) assess 

the robustness and computational efficiencies of the codes. Four thermohydrologic codes 

(CTOUGH, MULTIFLO, TOUGH2, and FEHMN) were evaluated and compared in terms of 

capability to simulate diverse conditions and overall computational efficiency.

Basagaoglu, H., K. Das, R. Fedors, R. Green, C. Manepally, S. Painter, O. Pensado, 

S. Stothoff, J. Winterle, and D. Wyrick. 10/24/2007. “Seepage Workshop Report.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. October 2007. 

20.06002.01.262.760, Q200710250004, ML072980846 [“Part A”], ML072980851 [“Part B”], 

ML072980850 [“Part C”] 

This report documents updates to the CNWRA staff’s technical basis for the seepage 

factors used in abstractions in TPA Version 5.1. Discussions include conceptualizations related 

to seepage such as ambient and thermal seepage, seepage-related parameters, and the 

technical basis for fluid and heat flow parameters used in TPA Version 5.1. 

 
10-3 

Das, K., C. Manepally, R. Fedors, and D. Basu. 09/16/2011. “Numerical and Experimental 

Study of In-Drift Heat and Mass Transfer Processes”. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. September 2011. 

20.14002.01.441.136, Q201109160001, ML112590142 

Fedors, R., S. Green, D. Walter, D. Farrell, S. Svedeman, F. Dodge, and R. Hart. 

03/18/2004. “Environmental Conditions in Drifts.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. March 2000. 

20.06002.01.091.410, Q200403220002, ML061310419 

This report presents in-drift temperature and relative humidity estimates for two 

scenarios, with drift degradation and without drift degradation. Environmental conditions along 

a typical drift are assessed to support estimates of the onset and duration of conditions 

conducive to corrosion, and to provide input for computational fluid dynamics models of in-drift 

air flow and moisture redistribution to model natural convection in heated drifts. 

Green, R.T. and S.L. Painter. 09/21/2007. Revised: “Numerical Simulation of the Drift-Scale 

Heater Test at Yucca Mountain: September 2002 Status Report.” San Antonio, Texas: Center 

for Nuclear Waste Regulatory Analyses: September 2007. 

20.06002.01262.709, Q200709240001, ML072670518 

This report documents the CNWRA thermohydrological modeling analysis of the 

Drift-Scale Heater Test to predict the temperature and saturation distribution in the rock during 

the heating and cooling phases of the test. The outcome of these predictive analyses is 

compared with temperatures measured during 4 years of heating. A CNWRA-developed 

multiphase code (MULTIFLO ) was used in all simulations. 

Green, R.T., F.T. Dodge, and G. Rice. 12/15/1994. “Prediction of Thermally-Driven Flow at 

Different Scales.” 1994. 

20.05704.023, Q199412270001, ML061370333 

This unpublished journal manuscript describes work conducted to assess fluid flow 

regimes at different scales, to assess work performed by DOE in their coupled ThermalHydrologic-Mechanical-Chemical tests. 

Green, R.T., F.T. Dodge, S.J. Svedeman, R.D. Manteufel, G. Rice, K.A. Meyer, and 

R.G. Baca. 05/25/1995. “Thermally Driven Moisture Redistribution in Partially Saturated Porous 

Media.” CNWRA 95-05. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

January 1995. 

20.05704.027, Q199505300001, ML040160742 

Also published as NUREG/CR-6348 

Green, R.T., C. Manepally, R.W. Fedors, and M.M. Roberts. 10/28/2008. “Examination of 

Thermal Refluxing in In-Situ Heater Tests.” 

20.14002.01.121.840, Q200810280007, ML083030097 

The report summarizes experimental data, theoretical developments, and evaluation of 

scaling relationships from studies conducted over a two-year period in the Thermohydrology 

Research Project. During the studies, a series of laboratory experiments was conducted in a 

variety of media to study the physics of thermally driven moisture redistribution. Principles of 

similarity theory were applied to develop dimensionless parameters to be used to predict 

thermohydrologic behavior at the field and repository scales from that observed at the laboratory 

scale. Numerical modeling of two-phase flow phenomena was used to evaluate the scaling 

theories and interpret the experimental results. 
10-4 

Green, R., R Manteufel, S. Svedeman, and F. Dodge. 04/08/1992. “Theoretical and 

Experimental Investigation of Thermo-Hydrologic Processes in a Partially Saturated, Fractured 

Porous Medium: A Summary of Work Through December 1991.” CNWRA 92-006. San 

Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. April 1992. 

20.03704.023, Q199204130001, ML040330762 

The Thermohydrology Research Project was undertaken in 1989 by CNWRA to assess 

coupled interactions, identify a representative elementary volume for unsaturated fractured rock, 

assess the role of fractures with regard to impeding or augmenting groundwater flow, identify 

those parameters critical to understanding the heat and mass transfer in the geologic system, 

extrapolate laboratory and field data and model validation. The purpose of the project was to 

expand the knowledge base of thermohydrologic phenomena, primarily derived from studies of 

geothermal systems, soil physics, and the drying of porous media, to conditions more applicable 

to the proposed high-level waste repository in a zone of highly fractured, low-permeability rock. 

This report summarizes the activities conducted and results of the program in its first year or so. 

(Also published as NUREG/CR-6026.) 

Green, R., S. Painter, B. Fratesi, C. Manepally, and G. Walter. 08/28/2003. “Status Report 

for Multiphase Numerical Simulation.” CD-ROM includes Appendixes A thru G. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 2003. 

20.06002.01.091.330, Q200309020006, ML040350704 

This report documents analyses conducted by the CNWRA to evaluate conceptual 

models and key property value assignments in numerical models used to simulate heat and 

mass transfer processes. The assessment used results from two experiments, one of which 

was conducted at laboratory scale by CNWRA staff and the other by the DOE at the field scale 

at the Exploratory Studies Facility at Yucca Mountain. The objective of the analyses was to 

evaluate the importance and effects of conceptual model selection, boundary condition 

prescription, and property value assignment. A CNWRA-developed multiphase modeling code 

(MULTIFLO, Version 1.5.2) was used to perform all the simulations. 

Hsiung, S.-M. and A.H. Chowdhury. 03/27/2003. “Final Report for DECOVALEX III Task 2C: 

Thermal-Mechanical Modeling of the Drift-Scale Heater Test at Yucca Mountain.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. March 2003. 

20.06002.01.101.310, Q200304010005, ML033640578 

Hsiung, S.-M., A.H. Chowdhury, and M.S. Nataraja. “Numerical Simulation of 

Thermal-Mechanical Processes Observed at the Drift-Scale Heater Test at Yucca Mountain, 

Nevada, USA.” International Journal of Rock Mechanics and Mining Sciences. Vol. 42. 

No. 5–6. pp. 652–666. July–September 2005. 

Hughson, D.L. and F.T. Dodge. “The Effect of Cavity Wall Irregularities on Seepage Exclusion 

from Horizontal Cylindrical Underground Openings. Journal of Hydrology. Vol. 228. 

pp. 206–214. 2000. 

Lichtner, P.C. and J.C. Walton. 12/30/1994. “Near-Field Liquid-Vapor Transport in a Partially 

Saturated High-Level Nuclear Waste Repository.” CNWRA 94-022. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. October 1994. 

20.05702.723450, Q199411010003, ML040160575 

The report describes an auxiliary CNWRA analysis conducted to estimate the time to 

wetting and fluid fluxes in the proposed repository at Yucca Mountain. The heat transfer and 

two-phase flow conditions in the repository were analyzed for the various heat loadings, with 

calculations performed using a CNWRA version (CTOUGH ) of the VTOUGH computer code. 
10-5 

Manepally, C., S. Green, F. Viana, and R. Fedors. 04/16/2007. “Evaluation of In-Drift Heat 

Transfer Processes.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

April 2007. 

20.06002.01.262.720, Q200704170002, ML071070508 

This report summarizes CNWRA investigations of the combined effect of the thermal 

processes and moisture redistribution in drifts using laboratory and numerical models. In 

particular, this report describes an intermediate scale (20-percent of drift scale) experiment and 

a related numerical model that were developed to provide confidence in the modeling 

capabilities. The experimental setup simulates the effects of uniform and nonuniform heat load 

distributions between the waste packages.

Manepally, C., A. Sun, R. Fedors, and D. Farrell. 06/30/2004. “Drift-Scale 

Thermohydrological Process Modeling—In-Drift Heat Transfer and Drift Degradation.” 

CNWRA 2004-05. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

July 2004. 

20.06002.01.091.420, Q200407020002, ML042160447 

This report describes a coupled thermohydrological detailed process model that 

integrates in-drift and near-field heat transfer processes. Such process models provide the 

in-drift and near-field thermohydrological conditions that are needed to determine the 

composition of pore water that may contact the waste package and to evaluate the potential of 

corrosion of waste packages, and they serve as a basis for model abstractions used in 

performance assessment. A two-dimensional drift-scale model using the MULTIFLO code 

(Version 2.0) was developed as part of this study. In addition, a separate two-dimensional 

drift-scale model was developed to incorporate the effects of drift degradation. The report also 

contains results of sensitivity analyses of significant parameters and a comparison of results 

with previous model conclusions. 

Manteufel, R.D. “Effects of Ventilation and Backfill on a Mined Waste Disposal Facility.” 

Nuclear Engineering and Design. Vol. 172, No. 1–2. pp. 205–219. 1997. 

Manteufel, R., M. Ahola, D. Turner, and A. Chowdhury. 03/04/1993. NUREG/CR–6021, 

“A Literature Review of Coupled Thermal-Hydrologic-Mechanical-Chemical Processes Pertinent 

to the Proposed High-Level Nuclear Waste Repository.” CNWRA 92-011. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. July 1993. 

20.05702.023.010.001, Q199303080003, ML012750463 

 The literature review focuses on identifying coupling mechanisms between individual 

processes and assessing their importance (i.e., if the coupling is important, potentially 

important, or negligible). The significance of considering thermal-hydrologic-mechanicalchemical coupled processes lies in whether or not the processes impact the design and/or 

performance objectives of the repository. 

Phillips, O.M.. . “Infiltration of a Liquid Finger Down a Fracture Into Superheated Rock.” 

Water Resources Research. Vol. 32, No. 6. pp. 1660–1670. 1996. 

This article describes an analysis conducted to estimate the thermal protection from 

focused liquid infiltration in fractures. The model accounts for the heat transfer and two-phase 

vaporization expected to control focused liquid infiltration into hot dry rock. The rate of liquid 

penetration and the maximum stable penetration depth are estimated using both scaling 

principles and numerical calculations. 
10-6 

Mintz, T., R. Pabalan, and C. Manepally. 09/23/2011. “Bench-Scale Tests of a Yucca 

Mountain Heated Drift Environment.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 2011. 

20.14002.01.441.153, Q201109230001, ML112660404 

Mohanty, S. “Effect of Multiphase Fluid Saturation on the Thermal Conductivity of Geologic 

Media.” Journal of Physics D. Applied Physics. Vol. 30. p. L80–L84. 1997. 

Mohanty, S. and G. Adams. 01/13/2006. “An Abstracted Model for Estimating Temperature 

and Relative Humidity in the Proposed Repository at Yucca Mountain.” (unpublished 

manuscript) 

20.06002.01.352.609, Q200601190001, ML071690513 

The paper describes an analysis conducted to estimate the thermal protection from 

focused liquid infiltration in fractures. The model accounts for the heat transfer and two-phase 

vaporization expected to control focused liquid infiltration into hot dry rock. The rate of liquid 

penetration and the maximum stable penetration depth are estimated using both scaling 

principles and numerical calculations. 

Murphy, W.M., C.J. Freitas, and P.C. Lichtner. 12/12/1995. “A Numerical Model for the 

Evolution of the Carbon System Geochemistry at the Proposed Nuclear Waste Repository at 

Yucca Mountain, Nevada, USA.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. 1995. 

20.05702.723.545, Q199603060014, ML061370439 

This paper summarizes the theoretical framework developed to describe liquid and gas 

phase transport coupled with the local equilibrium carbon system chemistry and near-field 

thermohydrologic conditions. The paper presents some simulation results for the proposed 

high-level waste repository. 

Murphy, W.M., R.T. Pabalan, J.D. Prikryl, and C.J. Goulet. “Reaction Kinetics and 

Thermodynamics of Aqueous Dissolution and Growth of Analcime and Na-Clinoptilolite at 

25 degrees C.” American Journal of Science. Vol. 296. pp. 128–186. 1996. 

This paper describes low-temperature (25 °C), long-term (up to 2.6 yr) batch-type 

dissolution and precipitation experiments that were conducted to examine reaction kinetics and 

thermodynamics of aqueous dissolution and growth of analcime and Na-clinoptilolite at pH 

values close to 9. 

Ofoegbu, G.I., A.C. Bagtzoglou, R.T. Green, and M. Muller. “Effects of Perched Water on 

Thermally Driven Moisture Flow at the Proposed Yucca Mountain Repository for High Level 

Waste.” Nuclear Technology. Vol. 125, No. 2. pp. 235–253. 1999. 

20.05708.661, Q199709030002 

Ofoegbu, G.O., S. Painter, R. Chen, R.W. Fedors, D.A. Ferrill. “Geomechanical and Thermal 

Effects on Moisture Flow at the Proposed Yucca Mountain Nuclear Waste repository.” Nuclear 

Technology. Vol. 134. p. 241–262. 2001. 

Ofoegbu, G.I., A. Ghosh, M.P. Ahola, S.-M. Hsiung, and A.H. Chowdhury. 08/30/1995. 

“Evaluation of ABAQUS as a Compliance Determination Computer Code.” CNWRA 95-016. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 1995. 

20.05702.623, Q199509210012, ML040330880 

This work evaluated the computer code ABAQUS to determine whether the code 

would be suitable as a compliance-determination computer code to assess the impact of 
10-7 

thermal-mechanical effects on near-field fluid flow and, in turn, on the capability of the proposed 

repository to provide effective isolation of the proposed types and quantities of radioactive 

waste. Therefore, the code was evaluated with respect to its capabilities to model coupled 

thermal, mechanical, and hydrologic processes in a fractured rock mass. 

Shukla, P.K., B. Dasgupta, S. Chocron, W. Li, and S. Green. 05/07/2007. “Thermal 

Modeling of a Storage Cask System: Capability Development.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. May 2007. 

20.06002.01.332.640, Q200705070003, ML071280826 

The report examines how the use of transportation, aging, and disposal canisters in a 

repository could affect the thermal regimes. 

Vidal, O. and W.M. Murphy. “Calculation of the Effect of Gaseous Thermodiffusion and 

Thermogravitation Processes on the Relative Humidity Surrounding a High Level Nuclear Waste 

Canister.” Waste Management. Vol. 19. pp. 189–198. 1999. 
11-1 

11 CORROSION OF ENGINEERED MATERIALS 

Most of these reports and papers deal with waste package container corrosion processes; a few 

involve corrosion of drip shield materials and other metals. 

Agarwal, S. and P. Shukla. 09/15/2011. “Critical Crack Dimensions for Advective Flow of 

Aqueous Solutions Through Elliptical Stress Corrosion Cracks” September 2011. 

20.14002.01.441.188, Q201109150002, ML112580209 

Ahn, T., H. Jung, X. He, and O. Pensado. “Understanding Long-Term Corrosion of Alloy 22 

Container in the Potential Yucca Mountain Repository for High-Level Nuclear Waste Disposal.” 

Journal of Nuclear Materials. Vol 379, No. 1–3. pp. 33-41. 2008. 

Brossia, C.S. and G.A. Cragnolino. “Effect of Environmental Variables on Localized 

Corrosion of Carbon Steel.” Corrosion. Vol. 56. pp. 505–514. May 2000. 

Brossia, C.S. and G.A. Cragnolino. “Effect of Palladium on the Corrosion Behavior of 

Titanium.” Corrosion Science. Vol. 46, No. 7. pp. 1,693–1,711. July 2004. 

Brossia, C.S. and G.A. Cragnolino. “Effects of Environmental and Metallurgical Conditions on 

the Passive and Localized Dissolution of Ti-0.15%Pd.” Corrosion. Vol. 57, No. 9. 

pp. 768–776. 2001. 

Chiang, K. 09/02/2011. “Interactions Between Magma and Waste Containers.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.106, Q201109020014, ML112450439

Chiang, K. 09/02/2011. “Stress Corrosion Cracking of Weldment of Nuclear Waste Outer 

Container Material.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2011. 

20.14002.01.441.134, Q201109020012, ML112450432 

Chiang, K. and L. Yang. 09/23/2011. “Techniques for Monitoring Localized Corrosion at High 

Temperatures.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2011. 

20.14002.01.441.174, Q201109230002, ML112660316 

Chiang, K.T., D.S. Dunn, and G.A. Cragnolino. “Effect of Simulated Groundwater Chemistry 

on Stress Corrosion Cracking of Alloy 22.” Corrosion. Vol. 63. pp. 940–950. 2007. 

Chiang, K.-T., D.S. Dunn, Y.-M. Pan, O. Pensado, and P.K. Shukla. 12/21/2006. “Stress 

Corrosion Cracking for Waste Package Materials—Modeling and Experiments.” 

CNWRA 2007-01. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

December 2006. 

20.06002.01.322.620, Q200701020001, ML070030061 

Cragnolino, G.A. and N. Sridhar. “Localized Corrosion of a Candidate Container Material for 

High-Level Nuclear Waste Disposal.” Corrosion. Vol. 47. pp. 464–472. June 1991. 

 
11-2 

Cragnolino, G. and N. Sridhar. 02/19/1993. “Long-Term Stability of High-Level Waste 

Container Materials: I-Thermal Stability of Alloy 825.” CNWRA 93-003. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. February 1993. 

20.05704.043.103, Q199303020004, ML040200291 

Cragnolino, G. and N. Sridhar. 08/01/1992. “A Review of Stress Corrosion Cracking of 

High-Level Nuclear Waste Containers Materials—I.” CNWRA 92-021. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. August 1992. 

20.03704.042, Q199209140004, ML033640122 

This report reviews the literature on stress corrosion cracking (SCC) of the candidate 

container materials for the proposed Yucca Mountain repository site, including Fe-Cr-Ni alloys 

and copper-based alloys. The advantages and limitations of different stress corrosion cracking 

(SCC) test methods are discussed in terms of their suitability for determining parameters that 

can be used for long-term prediction of SCC resistance performance, followed by a detailed 

review of investigations conducted by various laboratories and a review of results available in 

the general literature for the materials considered.

Cragnolino, G.A., D.S. Dunn, S. Brossia, Y.-M. Pan, O. Pensado, and L. Yang. “Corrosion 

Behavior of Waste Package and Drip Shield Materials.” Nuclear Technology. Vol. 148, No. 2. 

pp. 166–173. 2004. 

Cragnolino, G.A., D.S. Dunn, N. Sridhar. “Environmental Factors in the Stress Corrosion 

Cracking of Type 316L Stainless Steel and Alloy 825 in Chloride Solutions.” Corrosion. Vol. 52, 

No. 3. pp. 194–203. 1996. 

Cragnolino, G.A., D.S. Dunn, and N. Sridhar. 11/02/1994. “Environmental Effects on Stress 

Corrosion Cracking of Type 316L Stainless Steel and Alloy 825 as High-Level Nuclear Waste 

Container Materials.” CNWRA 94-028. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. October 1994. 

20.05704.042.255, Q199411150002, ML040360661 

Cragnolino, G.A., H.K. Manaktala, and Y.-M. Pan. 05/23/1996. “Thermal Stability and 

Mechanical Properties of High-Level Radioactive Waste Container Materials: Assessment of 

Carbon and Low-Alloy Steels.” CNWRA 96-004. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. May 1996. 

20.05708.571, Q199607160007, ML040230612 

Cragnolino, G.A., S. Mohanty, D.S. Dunn, N. Sridhar, and T. Ahn. “An Approach to the 

Assessment of High-Level Radioactive Waste Containment I-Waste Package Degradation.” 

Nuclear Engineering and Design Journal. Vol. 201 pp. 289–306. September 2000. 

Cragnolino, G.A., Y.-M. Pan, D. Turner, and E. Pearcy. 01/15/2004. “Natural Analogs of 

High-Level Container Materials—Experimental Evaluation of Josephinite.” CNWRA 2004-02. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. January 2004. 

20.06002.01.081.340, Q200401190012, ML041390323 

 
11-3 

Cragnolino, G.A., H. Pennick, N. Sridhar, and T.Y. Torng. “Application of a Transient 

Crevice Corrosion Model to the Prediction of Performance of High-Level Nuclear Waste 

Container Materials.” Life Predictions of Corrodible Structures. R.N. Parkins, ed. 

Houston, Texas: NACE International. Vol. 1. pp. 429–453. 1994. 

Q199203100004, 20.03702.013 

The initiation of crevice corrosion of austenitic container materials is examined through 

an extension of the Watson-Postlethwaite model to higher temperatures. The model predicts 

that increasing the temperature will lower the crevice corrosion initiation time, mainly through its 

effect on the hydrolysis equilibria. 

Cragnolino, G., N. Sridhar, J. Walton, R. Janetzke, T. Torng, J. Wu, and P. Nair. 

12/17/1994. “Substantially Complete Containment–Example Analysis of a Reference 

Container.” CNWRA 94-003. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. January 1994. 

20.05702.551.410, Q199403160011, ML033640232 

This report presents the analyses and results of an example problem conducted in 

support of evaluating the “substantially complete containment” rule for waste packages in 

10 CFR Part 60. Several models representing the repository thermal fields, near-field 

environment, corrosion of container materials, including localized corrosion and stress corrosion 

cracking, as well as mechanical failures were coupled to calculate the time-to-wetting and the 

time-to-failure of waste packages for an unsaturated repository site. A probabilistic method was 

adapted to generate cumulative distribution functions (CDFs) for failures of multiple waste 

packages arranged in a simulated square repository. For evaluating the various corrosion 

processes, the corrosion potential is used as a key parameter in conjunction with critical 

potentials for localized corrosion. This concept is shown to be a generally powerful approach 

for evaluating waste package lifetimes in a geologic repository. 

Csontos, A., T. Ahn, A. Passarelli, Y.-M. Pan, D.S. Dunn, and L. Yang. “The Evaluation of 

Corrosion Processes for Engineered Barrier Systems.” JOM. Vol. 57, No. 1. pp. 36-42. 2005. 

Csontos, A.A., Y.-M. Pan, D.S. Dunn, L. Yang, and G.A. Cragnolino. “The Effect of Potential 

and Aging on the Pb-Assisted Stress Corrosion Cracking Susceptibility of Alloy 22 Gas 

Tungsten Arc-Welded Weldments.” Metallurgical and Materials Transactions A—Physical 

Metallurgy and Materials Science. Vol. 36A, No. 5. pp. 1,169–1177. 2005. 

Dunn, D.S. and G.A. Cragnolino. 08/01/1997. “An Analysis of Galvanic Coupling Effects on 

the Performance of High-Level Waste Container Materials.” CNWRA 97-010. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 1997. 

20.05708.761.730, Q199709240002, ML040200062 

Dunn, D.S., M.B. Bogart, C.S. Brossia, and G.A. Cragnolino. “Corrosion of Iron Under 

Alternating Wet and Dry Conditions.” Corrosion. Vol. 56. pp. 470–481. May 2000. 

Dunn, D.S., G.A. Cragnolino, and N. Sridhar. “An Electrochemical Approach to Predicting 

Long-Term Localized Corrosion of Corrosion-Resistant High-Level Waste Container Materials.” 

Corrosion. Vol. 56. pp. 90–104. January 2000. 

Dunn, D.S., G.A. Cragnolino, and N. Sridhar. “Effect of Galvanic Coupling Between 

Overpack Materials of High-Level Nuclear Waste Containers.” Corrosion. Vol. 56. 

pp. 598–610. June 2000. 
11-4 

Dunn, D.S., G.A. Cragnolino, and N. Sridhar. 06/13/1997. “An Electrochemical Approach to 

Predicting Long-Term Localized Corrosion of Corrosion Resistant Container Materials.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. June 1997. 

20.05708.561, Q199708150002, ML040200176 

This report identifies corrosion potential and the repassivation potential as useful 

parameters to predict the long-term localized corrosion susceptibility for corrosion resistant 

candidate container materials such as type 316L stainless steel and alloy 825. This conclusion 

is based on laboratory tests that have demonstrated that pitting and crevice corrosion are 

initiated when the corrosion potential of the material exceeds the repassivation potential for 

localized corrosion. Once initiated, the propagation rate for the localized attack will result in 

rapid penetration of the waste packages. However, no localized corrosion can be initiated and 

all active corrosion sites repassivate when the corrosion potential of the material is lower than 

the repassivation potential. 

Dunn, D., D. Daruwalla, and Y.-M. Pan. 10/28/2003. “Effect of Fabrication Processes on 

Material Stability—Characterization and Corrosion.” CNWRA 2004-01. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. October 2003. 

20.06002.01.081.320, Q200311060005, ML040480532 

This report presents results of CNWRA experiments, as well as a review of DOE 

evaluations, on the effects of fabrication processes such as welding and annealing on the 

microstructure, uniform corrosion rate, localized corrosion susceptibility, and stress corrosion 

cracking resistance of Alloy 22.

Dunn, D.S., Y.-M. Pan, and K.T. Chiang. 03/30/2005. “Microstructural Analyses and 

Mechanical Properties of Alloy 22.” CNWRA 2005-03. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. March 2005. 

20.06002.01.102.420, Q200503310003, ML050910074 

Dunn, D.S., Y.-M. Pan, K.T. Chiang, L. Yang, G.A. Cragnolino, and X. He. “The Localized 

Corrosion Resistance and Mechanical Properties of Alloy 22 Waste Package Outer Containers.” 

JOM. Vol. 57, No. 1. pp. 49–54. January 2005. 

Dunn, D.S., Y.-M. Pan, L. Yang, and G.A. Cragnolino. “Localized Corrosion Susceptibility of 

Alloy 22 in Chloride Solutions: Part 1—Mill-Annealed Condition.” Corrosion. Vol. 61. 

pp. 1,078–1,085. November 2005. 

Dunn, D.S., O. Pensado, Y.-M. Pan, R.T. Pabalan, L. Yang, X. He, and K.T. Chiang. 

12/19/2005. “Passive and Localized Corrosion of Alloy 22 —Modeling and Experiments, 

Revision 1.” CNWRA 2005-02. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses: December 2005 

20.06002.01.322.500, Q200512190006, ML071560057 

Dunn, D., N. Sridhar, and G. A. Cragnolino. “Effects of Surface Chromium Depletion on 

Localized Corrosion of Alloy 825 as a High-Level Nuclear Waste Container Material.” 

Corrosion. Vol. 51, No. 8. pp. 618–624. 1995. 

Dunn, D.S.. N. Sridhar, and G.A. Cragnolino. “Long-Term Prediction of Localized Corrosion 

of Alloy 825 in High-Level Nuclear Waste Repository Environments.” Corrosion. Vol. 52, No. 2. 

pp. 115–124. 1996. 
11-5 

Geesey, G. 06/20/1993. “A Review of the Potential for Microbially Influenced Corrosion of 

High-Level Waste Containers.” CNWRA 93-014. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. June 1993. 

20.05704.044.101, Q199306300001, ML040230184 

He, X. 09/27/2011. “Electrochemical Behavior and Passivity of Titanium Drip Shield Materials 

Under Immersion Conditions.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. September 2011. 

20.14002.01.441.151, Q201109270006, ML112700443 

This report documents the results of a previously unpublished set of experiments that 

evaluated the fundamental difference in corrosion behavior between Titanium Grades 7 and 29 

under immersion conditions. Cathodic and anodic polarization results show that both palladium 

in Titanium Grade 7 and ruthenium in Titanium Grade 29 influence the cathodic reaction kinetics 

and enhance the crevice corrosion resistance; however, palladium and ruthenium appeared not 

to influence much of the anodic dissolution behavior. Both materials showed high passivity and 

the passive film resistance appeared to be independent of temperature. Compared to Titanium 

Grade 7, Titanium Grade 29 showed lower passive film resistance however, the difference is 

not significant. 

He, X. and D.S. Dunn. 12/21/2005. “Crevice Corrosion Penetration Rate of Alloy 22 in 

Chloride-Containing Waters.” CNWRA 2006-001. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. December 2005. 

20.06002.01.322.500, Q200512280002, ML062440377 

This progress report presents the experimental results of the crevice corrosion 

propagation rates of Alloy 22 in chloride-containing waters. The results of the investigation 

indicate that, the stifling and arrest of crevice corrosion significantly decrease the actual values 

of crevice corrosion propagation rates even under the aggressive environmental conditions 

used in these laboratory tests. 

He, X. and D.S. Dunn. “Crevice Corrosion Penetration Rates of Alloy 22 in Chloride-Containing 

Waters.” Corrosion. Vol. 63. pp. 145–158. 2007. 

He, X. and T. Mintz. “Localized Corrosion of Alloy 22 in the Yucca Mountain Repository 

Environment.” Journal of Metals. Vol. 60. pp. 44–51. 2008. 

The main purpose of this paper is to summarize work conducted to evaluate (i) the 

effects of environmental conditions relevant to the potential Yucca Mountain repository, 

metallurgical states (e.g., mill-annealed and welded plus solution annealed), and similar and 

dissimilar metal crevices on the crevice corrosion susceptibility of Alloy 22, and (ii) crevice 

corrosion propagation behavior by contacting to Alloy 22 or Titanium Grade 7. The results have 

shown that crevice corrosion susceptibility of Alloy 22 increased with increasing chloride 

concentration, temperature, and chloride-to-nitrate concentration ratios. Fabrication processes 

such as welding plus solution annealing also increased the localized corrosion susceptibility of 

Alloy 22. 

He, X. and T. Mintz. “Quantitative Characterization of Alloy 22 Crevice Corrosion Damage 

Profiles.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. April 2011. 

20.14002.01.441.156, Q200909230002, ML092660562 

Three- and two-dimensional (3-D and 2-D) laser profilometry scans were performed to 

accurately and quantitatively characterize the corrosion damage profiles. Laser scans are more 

sensitive to variations in penetration sites, leading to larger maximum crevice corrosion 

penetration depths measured than those previously obtained by optical microscope. For Alloy 
11-6 

22, crevice corrosion attack may have initially followed metallurgical features such as grain 

boundaries. 

He, X. , T. Ahn, and T. Sippel. 09/06/2011. “Corrosion of Borated Stainless Steel in Liquid 

Water and Vapor.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2011. 

20.14002.01.441.138, Q201109060002, ML112490365 

In this study, borated 304B4 and 304B5 stainless steels were exposed to the liquid and 

vapor phases of simulated ground water at 60, 75, and 90 °C [140, 167, and 194 °F] for about 3 

months. It was found that some specimens exposed to vapor at 75 and 90 °C [167 and 194 °F] 

suffered pitting corrosion, but pitting corrosion was not observed at 60 °C [140 °F] or from the 

liquid exposure at 75 and 90 °C [167 and 194 °F]. At all three temperatures, the general 

corrosion rates of 304B4 were less than 80 nm/yr [0.0032 mil/yr] and those of 304B5 were less 

than 600 nm/yr [0.024 mil/yr]. 

He, X., B. Brettmann, and H. Jung. “Effects of Test Methods on Crevice Corrosion 

Repassivation Potential Measurements of Alloy 22.” Corrosion. Vol. 65. pp. 449–460. 2009. 

The relative susceptibility of Alloy 22 to crevice corrosion is evaluated through the 

measurement of crevice corrosion repassivation potential (Ercrev) using electrochemical test 

methods. The main purpose of the work described in this paper is to verify some Ercrev values 

reported in the literature and investigate the effects of different electrochemical test methods on 

the measurement of Ercrev. . 

He. X., D.S. Dunn, and A.A. Csontos. 01/08/2008. “Crevice Corrosion Initiation and 

Propagation of Similar and Dissimilar Metal Couples in the Engineered Barrier System of the 

Potential Yucca Mountain Repository.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. November 2007. 

20.06002.01.322.720, Q200801080001, ML080080465 

The report describes the corrosion performance of the engineered barrier system 

materials in sodium chloride and magnesium chloride solutions at 95 °C [203 °F]. Five types of 

crevices were evaluated: (i) Type 316L stainless steel to mill-annealed Alloy 22, (ii) millannealed Alloy 22 to mill-annealed Alloy 22, (iii) welded plus solution annealed Alloy 22 to 

mill-annealed Alloy 22, (iv) mill-annealed Alloy 22 to Titanium Grade 7, and (v) welded plus 

solution annealed Alloy 22 to Titanium Grade 7. Except for Type 316L stainless steel, all other 

metal-to-metal crevices were less susceptible to crevice corrosion than the corresponding 

metal-to-polytetrafluoroethylene crevices. 

He, X., D.S. Dunn, and C.S. Csontos. “Corrosion of Similar and Dissimilar Metal Crevices in 

the Engineered Barrier System of a Potential Nuclear Waste Repository.” Electrochimica Acta. 

Vol. 52. pp. 7,556–7,569. 2007. 

Jung, H., T. Ahn, and T. Mintz. 09/06/2011. “Corrosion of Stainless Steel Type 316L in a 

Seepage Water Dripping Environment.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 2011. 

20.14002.01.441.186, Q201109060003, ML112490377 

Jung, H., X. He, T. Ahn, T. Mintz, and R. Pabalan. 09/02/2011. “Corrosion of Alloy 22 and 

Titanium Alloys Under Seepage Water Dripping Condition.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.118, Q201109020011, ML112450427 
11-7 

Jung, H., T. Mintz, D.S. Dunn, O. Pensado, and T. Ahn. 10/12/2007. “A Review of the LongTerm Persistence of the Passive Film on Alloy 22 in Potential Yucca Mountain Repository 

Environments.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. October 

2007. 

20.14002.01.171.735, Q200710150003, ML072880595 

Jung, H., T. Mintz, L. Yang, and T. Ahn. 01/13/2009. “Long-Term Persistence of the Passive 

Film on Alloy 22 at Elevated Temperatures in the Potential Yucca Mountain Repository 

Environment.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

January 2009 

20.14002.01.171.820, Q200901130004, ML090220175 

This report documents an evaluation of the long-term persistence of the passive film on 

Alloy 22 (Ni-22Cr-13Mo-4Fe-3W) at elevated temperatures {e.g., above 100 °C [212 °F]}. Two 

conditions are evaluated: (i) passive film stability with respect to composition and structure and 

(ii) the effects of anodic sulfur segregation on stability. 

Jung, H., L. Yang, and T. Ahn. 09/23/2011. “An Electrochemical Study on Passivation of 

Alloy 22 in Chloride-Containing Solutions With and Without Sulfur.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.012.020, Q201109230010, ML112660508 

Larose, S. and R.A. Rapp. 03/07/1997. “Review of Low-Temperature Oxidation of Carbon 

Steels and Low-Alloy Steels for Use as High-Level Radioactive Waste Package Materials.” 

CNWRA 97-003. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

February 1997. 

20.05708.571.775, Q199705310004, ML040200112 

Pan, Y.-M., C.S. Brossia, G.A. Cragnolino, D.S. Dunn, G.D. Gute, and L. Yang. 10/29/2002. 

“Stress Corrosion Cracking and Hydrogen Embrittlement of Container and Drip Shield 

Materials.” CNWRA 2003-02. San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. October 2002. 

20.06002.01.081, Q200210300002, ML033640096 

Pan, Y.-M., K.T. Chiang, D.S. Dunn, X. He, O. Pensado, P. Shukla, and L. Yang. 

“Independent Evaluation of Waste Package Corrosion Performance Under Potential Repository 

Conditions.” Nuclear Technology. Vol. 163, No. 1. pp. 85–91. July 2008. 

This paper summarizes the results of laboratory measurements and model analyses 

focused on uniform, localized, and microbially influenced corrosion, and stress corrosion 

cracking of Alloy 22. 

Pan, Y.-M., D.S. Dunn, and G.A. Cragnolino. 02/20/2004. “Topologically Close-Packed 

Phase Precipitation and Thermal Stability in Alloy 22.” Metallurgical and Materials Transactions 

A. Vol. 36. pp. 1143–1151. 2005. 

This study evaluated the effects of fabrication processes such as short-term thermal 

aging, welding, and postweld solution annealing on the phase stability of Alloy 22. 

Pan, Y.-M., D.S. Dunn, and G.A. Cragnolino. “Effects of Environmental Factors and Potential 

on Stress Corrosion Cracking of Fe-Ni-Cr-Mo Alloys in Chloride Solutions.” Environmentally 

Assisted Cracking: Prediction Methods for Risk Assessment and Evaluation of Materials, 

Equipment, and Structures. ASTM STP 1401. R.D. Kane, ed. ASTM. West Conshohocken, 

Pennsylvania. pp. 273–288. 2000. 
11-8 

Pan, Y.M., D.S. Dunn, G.A. Cragnolino, and N. Sridhar. “Grain Boundary Chemistry and 

Intergranular Corrosion in Alloy 825.” Metallurgical and Materials Transactions A. Vol. 31A. 

pp. 1,163–1,173. 2000. 

Pan, Y.-M., N. Sridhar, D.S. Dunn, and G.A. Cragnolino. 05/04/1995. “Effect of Specimen 

Preparation Procedures on Chromium Depletion and Precipitation Chemistry in Alloy 825 by 

Analytical Electron Microscopy.” Journal of Materials Science Letters. Vol. 15, No. 6. 

pp. 522-524. 1996. 

Pensado, O. and R. Pabalan. “Probabilistic Methodology to Estimate Environmental 

Conditions for Localized Corrosion and Stress Corrosion Cracking of Alloy 22 in a High-Level 

Radioactive Waste Repository Setting.” Journal of Nuclear Materials. Vol. 381, Issue 3, 15. 

Pp 231–241. November 2008. 

Pensado, O. and R.T. Pabalan. 09/15/2011. “Assessment of Probability of Localized 

Corrosion of Alloy 22 Waste Package Material in a Proposed High-Level Waste Geologic 

Repository at Yucca Mountain, Nevada.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 2011. 

20.14002.01.441.146, Q201109150004, ML112580219 

Pensado, O., D.S. Dunn, G.A. Cragnolino, and V. Jain. 10/25/2002. “Passive Dissolution of 

Container Materials—Modeling and Experiments.” CNWRA 2003-01. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. October 2002. 

20.06002.01.081.230, Q200210300001 ML033640090 

Shukla, P., R. Pabalan, and X. He. 09/21/2011. “Crevice Chemistry Model Development for 

Nickel-Based Alloys and Analysis of Model Results In View of Literature Information.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.166, Q201109210001, ML112640376 

Sridhar, N. 09/28/1992. “A Preliminary Assessment of Pitting Corrosion Models.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 1992. 

20.03702.013, Q199210120007, ML033650080 

Sridhar, N. and G. A. Cragnolino. “Effects of Environment on Localized Corrosion of 

Copper-Based, High-Level Waste Container Materials.” Corrosion. Vol. 79, No 12. 

pp. 967–976. 1993. 

This paper examined the effects of environmental factors on localized corrosion of 

copper-based materials. The environmental factors examined were those present in the 

groundwater near Yucca Mountain: bicarbonate, chloride, and sulfate. 

Sridhar, N. and G. A. Cragnolino. “Applicability of Repassivation Potential for Long-Term 

Prediction of Localized Corrosion of Alloy 825 and Type 316L Stainless Steel.” Corrosion. 

Vol. 49, No 11. pp. 885–894. 1993. 

Sridhar, N. and G.A. Cragnolino. “Stress Corrosion Cracking of Nickel-Base Alloys. Stress

Corrosion Cracking: Materials Performance and Evaluation.” Russell H. Jones, ed. 

Materials Park, Ohio: ASM International. pp. 131–179. 1992. 
11-9 

Sridhar, N. and G. Cragnolino. “Stress Corrosion Cracking of Nickel-Base Alloys.” Chapter 5 

(pp 131–179) in Stress-Corrosion Cracking: Material Performance and Evaluation. R.H. Jones, 

ed. Materials Park, Ohio: American Society of Metallurgists (ASM) International. 1992. 

Sridhar, N. and D.S. Dunn. “Effect of Applied Potential on Changes in Solution Chemistry 

Inside Crevices on Type 304L Stainless Steel and Alloy 825.” Corrosion. Vol. 50, No. 11. 

pp. 847–872. 1994. 

Sridhar, N. and D.S. Dunn. “In-Situ Study of Salt Stability in Simulated Pits of Nickel by 

Raman and Electrochemical Impedance Spectroscopies.” Journal of the Electrochemical 

Society. Vol. 144, No. 12. pp. 4,243–4,253. 1997. 

Sridhar, N., G.A. Cragnolino, and D. Dunn. 02/01/1993. “Experimental Investigations of 

Localized Corrosion of High-Level Waste Container Materials.” CNWRA 93-004. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. February 1993. 

20.05704.041, Q199303020001, ML040200255 

Sridhar, N., G.A. Cragnolino, and D.S. Dunn. 05/19/1995. “Experimental Investigations of 

Failure Processes of High-Level Radioactive Waste Container Materials.” CNWRA 95-010. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. May 1995. 

20.05704.041, Q199506060001, ML040220295 

This report presents the results of five years of research activities in the Integrated 

Waste Package Experiments Research Project. Experiments focused on localized corrosion, 

stress corrosion cracking, materials thermal stability, and hydrogen embrittlement of austenitic 

Fe-Cr-Ni-Mo alloys selected as candidate materials for the construction of high-level radioactive 

waste containers. 

Walton, J.C., G.A. Cragnolino, and S.K. Kalandros. “A Numerical Model of Crevice 

Corrosion for Passive and Active Metals.” Corrosion. Vol. 38, No. 1. pp. 1–18. 1996. 

Yang, L. 04/21/2006. “Corrosion of Alloy 22 in Concentrated Nitrate and Chloride Salt 

Environments at Elevated Temperatures—Progress Report.” CNWRA 2006-02. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. April 2006. 

20.06002.01.322.610, Q200604250001, ML061430298 

The objectives of this work were to (i) study the chemistry of the liquid formed by the 

nitrate-chloride salt mixtures and the vapor above the liquid, and (ii) investigate the localized 

and general corrosion behavior of Alloy 22 in the liquid and vapor environment in an 

ambient-pressure system that was not deaerated to simulate the potential Yucca Mountain drift 

conditions at elevated temperatures. 

Yang, L., R.T. Pabalan, and M.R. Juckett. “Deliquescence Relative Humidity Measurements 

Using an Electrical Conductivity Method.” Journal of Solution Chemistry. Vol. 35. pp. 583–604. 

2006. 

Yang, L., R. Pabalan, P. Shukla, M. Juckett, X. He, K.T. Chiang, H. Gonzalez, and T. Ahn. 

03/14/2011. “Corrosion of Alloy 22 Induced by Dust Deliquescence Brines.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. March 2011. 

20.14002.01.441.830, Q201103140001 ML110730489 

During the preclosure period of a potential Yucca Mountain repository, the repository 

drift would be ventilated and atmospheric aerosols and tunnel dusts could be deposited onto the 

waste package surfaces by the ventilation, leading to the accumulation of small amounts of 
11-10 

hygroscopic salts on the waste package surfaces. The hygroscopic salts could deliquesce and 

form a brine solution on the waste package surfaces when the relative humidity of the in-drift 

environment is near or above the salt’s deliquescence relative humidity. This report evaluates 

Alloy 22 corrosion by the deliquescence brines under potential repository conditions. 
12-1 

12 STRUCTURAL PERFORMANCE OF ENGINEERED MATERIALS: 

CREEP, EMBRITTLEMENT, AND EARLY FAILURE MECHANISMS 

Ankem, R. and T. Wilt. 10/24/2007. “A Literature Review of Low Temperature (<0.25T mp) 

Creep Behavior of a, a-ß, and ß Titanium Alloys.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. October 2007. 

20.14002.01.191, Q200710250006, ML072980893, ML072980894, ML072980897 

This report surveys the current literature pertinent to the long-term, low temperature 

creep behavior of Titanium Grades 7 and 24 or reasonable surrogates. Specifically, this report 

investigates the creep mechanisms of slip, twinning, grain boundary sliding, alpha-beta interface 

sliding, Widmanstatten colony boundary sliding, and stress-induced martensite. Additional 

parameters such as the microstructure of phases, chemical composition, texture, stress type, 

and cold work are also evaluated. 

Chan, K.S. 09/28/2007. “An Assessment of Delayed Hydride Cracking in Zirconium Alloy 

Cladding Tubes Under Stress Transients.” 

20.06002.01.222.740, Q200710010001, ML112650048 

This document is an unpublished manuscript. 

Chan, K.S. and Y. Lee. “A Fracture Mechanics-Based Model for Assessing the Mechanical 

Failure of Nuclear Fuel Rods Due to Rock Fall.” Nuclear Engineering and Design, Vol. 201, 

pp. 209-226. 2000. 

Hsiung, S.-M. and S. Mohanty. “An Abstracted Model for Assessing the Effect of Seismically 

Induced Rock Fall on the Waste Package Performance for High-Level Radioactive Waste 

Disposal.” PSAM 5-Probabilistic Safety Assessment and Management. S. Kondo, K. Furuta, 

eds. Frontiers Science Series 34. Universal Academy Press, Inc. Tokyo, Japan: Vol. 3. 

pp. 1,581–1,588. 2000. 

Ibarra, L., T. Wilt, G. Ofoegbu, and A. Chowdhury. 01/23/2007. “Structural Performance of 

Drip Shield Subjected to Static and Dynamic Loading.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. January 2007. 

20.06002.01.342.720, Q200701230005, ML070240131 

The report presents the result of a modeling study in which the drip shield structure is 

modeled using both a finite element model (ABAQUS) and an equivalent frame model 

(SAP2000). The finite element model verifies the structural response obtained from the drip 

shield frame model, and it provides information about the moment-rotation relationships of the 

drip shield sections and equivalent spring constants to account for drip shield–rubble interaction. 

The frame model is then used to evaluate the structural performance of the drip shield based on 

sensitivity studies and seismic analyses. 

Ibarra, L., T. Wilt, G. Ofoegbu, R. Kazban, F. Ferrante, and A.H. Chowdhury. 02/19/2007. 

“Drip Shield-Waste Package Mechanical Interaction.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. June 2006. 

20.06002.01.342.710, Q200702200001, ML070520335 

This study evaluates the potential mechanical interaction between the drip shield 

and the waste package caused by a collapsed drip shield system. This interaction is 

evaluated by means of finite element models developed in ABAQUS. The models include 

(i) two-dimensional, plane strain models of simple geometry but a very refined mesh, and (ii) a 

three-dimensional model that reproduces the overall performance of the drip shield-waste 

package interaction. The three-dimensional modeling is used to verify some of the assumptions 
12-2 

adopted in the plane strain models, and to estimate the contact length of the bulkhead. A 

sensitivity study is performed to evaluate the effect of demand and system parameter variation 

on the waste package capacity. The main results have been used to generate abstractions to 

update the Total-system Performance Assessment computer code. 

Jain, V., D. Daruwalla, and C. Fairbanks. 04/03/2003. “Assessment of Mechanisms for Early 

Waste Package Failures.” CNWRA 2003-05. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. March 2003. 

20.06002.01.081.310, Q200304090001, ML040350562 

This report reviews the U. S. Department of Energy (DOE) methodology for estimating 

early waste package failures using simulation data from the expert-system based simulation 

RR-PRODIGAL code and event-tree analysis to quantify probabilities of failure for various 

manufacturing defects. In addition, this report provides a review of other available information, 

and an analysis of weld flaws for the outer-lid closure weld. 

Sridhar N, G.A. Cragnolino, D.S. Dunn, and H.K. Manaktala. 04/21/1994. “Review of 

Degradation Modes of Alternate Container Designs and Materials.” CNWRA 94-010. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. April 1994 

20.05704.045.201, Q199404280001, ML033630647 

This report considered the performance of alternate container materials, including 

materials being considered for multipurpose canisters (MPCs), which would be a completely 

sealed canister containing spent fuel bundles that could be transferred within overpacks from 

the plants through intermediate storage sites to the eventual disposal site. The review focused 

on the structural characteristics of the MPC and noted that the mechanical integrity of the MPC 

materials, especially in the welds, can be impaired due to embrittlement under long-term 

exposure to temperatures of 200–300 °C [392–572 °F]. 

Sridhar, N., B.E. Wilde, C. Manfredi, S. Kesavan, and C. Miller. 06/27/1991. 

“Hydrogen Absorption and Embrittlement of Candidate Container Materials.” CNWRA 91-008. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. June 1991. 

20.03704.041, Q199107090036, ML040330594 

Tszeng, T.C. 09/18/2008. “Review of Analysis of Mechanisms for Early Waste Package and 

Drip Shield Failure. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2008. 

20.06002.01.322.630, Q200809180004, ML082630079 

This report addresses possible mechanisms for early failure of waste packages and drip 

shields that may allow water ingress into the failed waste package and lead to early release of 

radionuclides. In particular, this report reviews the early failure analysis of the waste package 

outer container and drip shield related to manufacturing-induced defects presented in the 

U.S. Department of Energy report titled Analysis of Mechanisms for Early Waste Package/Drip 

Shield Failure. 

Wilt, T., A. Chowdhury, and T. Ahn. 10/22/2010. “A Literature Review of the Structural 

Integrity of Analog Canisters.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. October 2010. 

20.14002.01.441, Q201010220001, ML112650310 

This report documents a literature review used to evaluate the structural behavior of 

DOE standardized spent nuclear fuel canister, Idaho Spent Fuel Project canisters, multi-canister 

overpacks, and high-level waste canisters. These canisters can be considered analogous to the 

transportation, aging, and disposal canister concept DOE has proposed. The primary objective 
12-3 

was to investigate different types of canisters and their structural robustness when subjected to 

a drop event at a number of drop orientations and heights. The process used to develop 

structurally robust DOE canister designs includes (i) using limited small- or full-scale testing to 

evaluate the proposed canister design, (ii) using visual inspection and pressure testing of 

dropped canisters to verify structural integrity, and (iii) comparing small- and full-scale test 

results with the corresponding three-dimensional finite element analyses that provide detailed 

stress–strain distributions to further examine canister structural integrity. 
13-1 

13 ROCK MECHANICS AND EXCAVATION STABILITY 

Ahola, M.A. 05/22/1997. “A Parametric Study of Drift Stability in Jointed Rock Mass–Phase II: 

Discrete Element Dynamic Analysis of Unbackfilled Drifts.” CNWRA 97-007. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. June 1997. 

20.05708.761.740, Q199710210003, ML040200090 

This report presents a discrete element analysis using the code UDEC (Version 3.0) to 

investigate the effect of repeated seismic loading, with peak underground accelerations ranging 

from 0.2 to 0.4g, on cumulative joint slip and failure around a heated and unsupported 

emplacement drift in the proposed repository at Yucca Mountain. 

Ahola, M.P., R. Chen, H. Karimi, S. Hsiung, and A.H. Chowdhury. 09/01/1996. 

“A Parametric Study of Drift Stability in Jointed Rock Mass–Phase I: Discrete Element 

Thermal-Mechanical Analysis of Unbackfilled Drifts.” CNWRA 96-009. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. September 1996. 

20.05708.671.640, Q199701230006, ML040230678 

The objective of this study was to identify thermal and site specific natural phenomena 

and rock mechanical and thermal parameters that may significantly influence the pre- and 

postclosure performance of the repository under heated and seismic conditions. In Phase I, a 

distinct element computer code (UDEC) was used to conduct a parametric investigation of 

emplacement drifts without backfill, rock support, and seismic load for 100 yr of heating.

Brady, B.H.G., S.-M. Hsiung, and A.H. Chowdhury. 01/01/1990. “Qualification Studies on 

the Distinct Element Code Universal Distinct Element Code (UDEC) Against Some Benchmark 

Analytical Problems.” CNWRA 90-004. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. January 1990. 

No comments available. 20.03704.033, Q199112190002, ML040690187 

This report presents the results of studies which assess the performance of the 

two-dimensional distinct element code, UDEC, in analysis of some benchmark problems in the 

mechanics of discontinuous rock. 

Brandshaug, T., B. Dasgupta, B.H.G. Brady, S.-M. Hsiung, and A.H. Chowdhury. 

02/01/1990. “Qualification Studies on the Finite Element Code Hondo II Against Some 

Benchmark Analytical Problems.” CNWRA 90-006. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. February 1990. 

20.03704.033, Q199107230015, ML040690163 

This report presents the results of studies that assess the performance of the 

two-dimensional finite element code, HONDO II, in analysis of some benchmark problems in the 

mechanics of discontinuous rock. 

Fox, D.J., D.D. Kana, and S.M. Hsiung. “Influence of Interface Roughness on Dynamic Shear 

Behavior in Joint Rock.” International Journal of Rock Mechanics and Mining Sciences. 

Vol. 35, No. 7. pp. 923–940. 1998. 

Ghosh, A. and S. Hsiung. 09/29/2011. “Effects of Tilted and Faulted Strata on Seismic 

Ground Motion.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2011. 

20.14002.01.441.160, Q201109290003 

 
13-2 

Ghosh, A., S.-M. Hsiung, and A.H. Chowdhury. 06/27/1995. “Seismic Response of Rock 

Joints and Jointed Rock Mass.” CNWRA 95-013. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. June 1995. 

20.05704.037.095.001, Q199507190003, ML040210700 

This report summarizes one component of the activities conducted in the Rock 

Mechanics research project. 

Hsiung, S.-M. and A.H. Chowdhury. 09/15/2011. “Seismic Effects on Soil-Structure 

Interactions.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 

2011. 

20.14002.01.441.172, Q201109150001, ML112580204 

Hsiung, S.-M., W. Blake, A.H. Chowdhury, and T.J. Williams. 03/01/1993. “Effects of 

Mining-Induced Seismic Events on a Deep Underground Mine.” Pure and Applied Geophysics.

Vol. 139, Nos. 3/4. pp. 741–762. 1992. 

This paper assesses the performance of an underground excavation at the Lucky Friday 

Mine in the Coeur d'Alene Mining District of Idaho that was subjected to repetitive episodes of 

mining-induced seismic activities. Step changes in displacement or in excavation closures were 

explained by the concept of stick-slip on joints or bedding planes within the rock mass. Through 

this mechanism, joint displacement is accumulated at joints or along a bedding plane in a 

progressive fashion, weakening the rock mass around an excavation and making it more 

susceptible to seismic impacts. 

Hsiung, S.-M., A.H. Chowdhury, W. Blake, M.P. Ahola, and A. Ghosh. 12/16/1992. “Field 

Site Investigation: Effect of Mine Seismicity on a Jointed Rock Mass.” CNWRA 92-012. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. December 1992. 

20.05704.034.031, Q199301200003, ML040200235 

This field study at the Lucky Friday Mine in northern Idaho indicated that rock mass 

deformation around an excavation after repetitive episodes of mine seismic events was caused 

by an accumulation of joint shear displacement, which gradually weakens the rock mass. The 

mechanism of joint displacement accumulation is analogous to stress fatigue phenomena 

commonly observed for natural or artificial materials. This implies that similar, or even more, 

damage to an excavation may occur due to a number of seismic events with relatively smaller 

magnitudes, as opposed to the damage due to a single seismic event with a very strong motion. 

Hsiung, S.-M., A. Ghosh, and A.H. Chowdhury. 01/31/1995. “Progress Toward a Fractal 

Representation of Rock Joint Roughness.” CNWRA 95-004. San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. January 1995. 

20.05702.623, Q199502070001, ML040210608 

Hsiung, S.-M., A. Ghosh, A.H. Chowdhury, and M.P. Ahola. 11/19/1993. “Evaluation of 

Rock Joints Model and Computer Code Universal Distinct Element Code (UDEC) Against 

Experimental Results.” CNWRA 93-024. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. December 1993. 

20.05704.033, Q199401030007, ML033640188 

 
13-3 

Kana, D.D., D.J. Fox, S.-M. Hsiung, and A.H. Chowdhury. 06/27/1995. “An Experimental 

Scale-Model Study of Seismic Response of an Underground Opening in Jointed Rock Mass.” 

CNWRA 95-012. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

June 1995. 

20.05704.034.095.001, Q199507190002, ML040210691 

This report describes the design and implementation of simulated seismic experiments 

and results for a 1/15 scale model of a jointed rock mass with a circular tunnel in the middle. 

Kana, D.D., D.C. Scheidt, B.H.G. Brady, A.H. Chowdhury, S.-M. Hsiung, and B.W. Vanzant. 

01/01/1990. “Development of a Rock Joint Dynamic Shear Test Apparatus.” CNWRA 90-005. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. January 1990. 

20.03704.032, Q199112190003, ML040780170 

This report describes the design, assembly, calibration, and operation of a rock joint 

dynamic shear test apparatus, as part of the Seismic Rock Mechanics Project. 

Ofoegbu, G. 09/23/2011. “Analysis of Spatial Variability of Rock-Mass Quality and 

Thermal-Mechanical Effects in Geologic Disposal of High-Level Nuclear Waste.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.178, Q201109230003,ML112660328 

Ofoegbu, G., R. Fedors, C. Grossman, S. Hsiung, L. Ibarra, C. Manepally, J. Myers, 

M. Nataraja, O. Pensado, K. Smart, and D. Wyrick. 04/11/2007. “Summary of Current 

Understanding of Drift Degradation and Its Effects on Performance at a Potential Yucca 

Mountain Repository.” Rev. 1. CNWRA 2006-02. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. January 2007. 

20.06002.01.342.650, Q200704120017, ML070650462 

This report is a summary of information and evaluations regarding the degradation of 

emplacement drifts and the effects of drift degradation on long-term performance of a proposed 

Yucca Mountain nuclear waste repository. 

Ofoegbu, G.I., K.J. Smart, and B. Dasgupta. “Assessing Effects of Thermal Loading on the 

Stability of Emplacement Drifts.” Nuclear Technology. Vol. 163. pp. 24–30. 2008. 

Read, R.S. and G.I. Ofoegbu. 06/14/2006. “Review of Tools and Techniques to Monitor 

Repository Excavations. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

June 2006. 

20.06002.01.191.620, Q200606160002, ML061740535 

The report provides a summary of tools and techniques for monitoring the stability of 

underground openings in rock that may be applicable to a potential Yucca Mountain repository. 

Monitoring methods typically used in and around underground openings and their suitability for 

monitoring in a repository environment of high temperature and radiation are reviewed. Means 

of interpreting measurements to identify and characterize damage around the underground 

openings are discussed, along with implications for developing a contingency plan for 

maintenance of the underground openings. 
14-1 

14 WASTE FORM PROPERTIES AND RADIONUCLIDE RELEASE 

Jain, V., G. Cragnolino, and L. Howard. 09/09/2004. “A Review Report on High Burnup 

Spent Nuclear Fuel—Disposal Issues.” CNWRA 2004-08. San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. September 2004. 

20.06002.01.081.410, Q200409170005, ML043020321 

Jung, H., T. Ahn, K. Axler, R. Pabalan, and D. Pickett. 09/08/2011. “Corrosion of SIMFUEL 

in Aerated Carbonate Solution Containing Calcium and Silicate.” San Antonio, Texas: Center 

for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.124, Q201109080001, ML112520488 

This report documents the results of a previously unpublished set of experiments that 

evaluated the corrosion behavior of simulated spent nuclear fuel (SIMFUEL). The purpose of 

the experiments was to confirm a range of dissolution rates of spent nuclear fuel in a repository 

relevant environment, specifically under oxiding conditions, and to assess the potential effect of 

radionuclide sorption onto the oxides formed on stainless steel. 

Manaktala, H.K. “Standard Test Methods for Determining Chemical Durability of Nuclear 

Waste Glasses: The Product Consistency Test (PCT).” American Society for Testing and 

Materials (ASTM) Nuclear Energy (I). ASTM Standard No. C1285-94. Vol. 12.01. pp. 1–18. 

1995. 

Manaktala, H. 03/01/1993. “Characteristics of Spent Nuclear Fuel and Cladding Relevant to 

High-Level Waste Source Term.” CNWRA 93-006. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. May 1993. 

20.05702.013.295, Q199305110010, ML040200340 

Manaktala, H.K. 09/01/1992. “An Assessment of Borosilicate Glass as a High-Level Waste 

Form.” CNWRA 92-017. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 1992. 

20.03702.232, Q199209150002, ML033650021 

Manaktala, H.K. 08/28/1992. “Leaching of Borosilicate Glass Using Draft ASTM Procedure for 

High- Level Waste.” CNWRA 92-018. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. August 1992. 

20.03702.232, Q199209100003, ML033640056 

Mohanty, S., R. Codell, T. Ahn, and G.A. Cragnolino. “An Approach to the Assessment of 

High-level Radioactive Waste Containment-II: Radionuclide Release from an Engineered 

Barrier System.” Nuclear Engineering and Design Journal. Vol. 201 pp. 307–325. 2000. 

Murphy, W.M. 05/07/1991. “Calculated Solubilities of Radioelements at 25 C in J-13 Well 

Water.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 1991. 

20.03702.065, Q199107160023, ML040210573 

Murphy, W.M. and R.T. Pabalan. 06/28/1995. “Review of Empirical Thermodynamic Data for 

Uranyl Silicate Minerals and Experimental Plan.” CNWRA 95-014. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. June 1995. 

20.05704.153.501, Q199507240003, ML040210708 

Experimental and natural analog data indicate that uranyl silicate minerals are likely to 

form as oxidation products of spent nuclear fuel in a high-level radioactive waste repository at 
14-2 

Yucca Mountain, Nevada. Although these minerals would control releases of uranium and 

possibly much of the radionuclide inventory of high-level waste, the fundamental thermodynamic 

properties of these minerals required for predictive modeling of their behavior are poorly known. 

This report describes an experimental plan that was developed to determine thermodynamic 

properties of uranyl silicate minerals through original experimentation and data interpretation. 

The plan involved the study of uranophane, soddyite, and schoepite solubilities at 25, 60, and 

90 °C [77, 140, and 194 °F]. This document also described experiments designed to determine 

the importance of coprecipitation reactions as mechanisms for limiting the release and transport 

of actinides such as plutonium and neptunium. 

Murphy, W.M. and E.L. Shock. “Environmental Aqueous Geochemistry of Actinides.” 

Uranium: Mineralogy, Geochemistry, and the Environment, Reviews in Mineralogy. P.C. Burns 

and R. Finch, eds. Washington, DC: Mineralogical Society of America. Vol. 38. pp. 221–253 

1999. 

Pan, Y.-M., V. Jain, and O. Pensado-Rodriguez. “Degradation of High-Level Waste Glass 

Under Simulated Repository Conditions.” Journal of Non-Crystalline Solids. Vol. 319, No. 1–2. 

pp. 74-88. May 2003. 

Pearcy, E.C., W.M. Murphy, and P.C. Goodell. 05/23/1990. “Element Mobility in Uranium 

Deposits of the Sierra Peña Blanca as a Natural Analog of Radionuclide Migration in a 

High-Level Nuclear Waste Repository.” P.C. Energy Resources of the Chihuahua Desert 

Region. El Paso, Texas: El Paso Geological Society, pp. 192-296. 1994. . 

Pearcy, E.C, J.D. Prikryl, W.M. Murphy, and B.W. Leslie. 05/25/1993. “Alteration of 

Uraninite From the Nopal I Deposit, Peña Blanca District, Chihuahua, Mexico, Compared to 

Degradation of Spent Nuclear Fuel in the Proposed U.S. High-Level Nuclear Waste Repository 

at Yucca Mountain, Nevada.” Applied Geochemistry. Vol. 9. pp. 713–732. 1994. 

Pearcy, E.C., J.D. Prikryl, W.M. Murphy, and B.W. Leslie. 06/01/1993. “Uranium Mineralogy 

of the Nopal I Natural Analog Site, Chihuahua, Mexico.” CNWRA 93-012. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. June 1993. 

20.05704.065, Q199307080003, ML033650119 

Pickett, D.A. 12/01/2005. “Effects of Spent Nuclear Fuel Uranyl Alteration Phases on 

Radionuclide Dissolved Concentration Limits.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. December 2005. 

20.06002.01.222.520, Q200512010005, ML053480220 

Prikryl, J.D. “Uranophane Dissolution and Growth in CaCl2-SiO2(aq) Test Solutions.” 

Geochimica et Cosmochimica Acta. Vol. 72. Pp. 4,508–4,520. 2008. 

ML070800453 

This paper examines the dissolution and growth of uranophane [Ca(UO2)2(SiO3OH)2 · 

5H2O] in Ca- and Si-rich test solutions. Uranium-bearing experimental solutions undersaturated 

and supersaturated with uranophane were reacted with synthetic uranophane and analyzed 

periodically over a 10 week period. Interpretation of aqueous solution data permitted extraction 

of a solubility constant for the uranophane dissolution reaction and a standard state Gibbs free 

energy of formation for uranophane. 
15-1 

15 FLOW AND TRANSPORT 

Radionuclide transport is affected by many mechanisms, including sorption and matrix diffusion. 

Those topics are included in this section, as are hydrogeological models of isothermal 

groundwater flow in unsaturated and saturated rocks. 

Ababou, R. 08/01/1991. NUREG/CR-5743, “Approaches to Large Scale Unsaturated Flow in 

Heterogeneous Stratified, and Fractured Geologic Media.” Washington, DC: U.S. Nuclear 

Regulatory Commission. 1991. 

20.03704.051, Q199107160004 

This report develops a broad review and assessment of quantitative modeling 

approaches and data requirements for large-scale subsurface flow in a radioactive waste 

geologic repository. The data review includes discussions of controlled field experiments, 

existing contamination sites, and site specific hydrogeologic conditions at Yucca Mountain. 

Local-scale constitutive models for the unsaturated hydrodynamic properties of geologic media 

are analyzed, with particular emphasis on the effect of structural characteristics of the medium. 

The report further reviews and analyzes large-scale hydrogeologic spatial variability from aquifer 

data, unsaturated soil data, and fracture network data gathered from the literature. Finally, 

various modeling strategies toward large-scale flow simulations are assessed, including direct 

high-resolution simulation, and coarse-scale simulation based on auxiliary hydrodynamic 

models such as single equivalent continuum and dual-porosity continuum. (This report is 

publicly available at http://www.osti.gov/energycitations/product.biblio.jsp?osti_id=138205.) 

Ahola, M. and B. Sagar. 01/10/1992. “Regional Groundwater Modeling of the Saturated Zone 

in the Vicinity of Yucca Mountain, Nevada, Iterative Performance Assessment—Phase II.” 

CNWRA 92-001. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

January 1992. 

20.03702.065, Q199201210006, ML040630369 

 As one of the auxiliary analyses in this iterative performance assessment, it was decided 

to simulate the flow field in the saturated unconfined region that contains Yucca Mountain. The 

specific objective of this analysis is to study the fluctuations in the water table in response to 

postulated changes in recharge rates and other modifications in geohydrologic structures. 

Armstrong, A., D.A. Farrell, S.L. Painter, and D.R. Turner. “Review of the Saturated Zone 

Flow and Transport Models Used to Support the Viability Assessment of the Proposed 

High-Level Waste Repository at Yucca Mountain.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. March 1999. ML033630097 

Baca, R.G., G.W. Wittmeyer, and R.W. Rice. 09/27/1996. “Analysis of Contaminant Dilution 

in Groundwater.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 1996. 

20.05708.771, Q199612160001, ML040230658 

In this scoping analysis, large-scale groundwater flow and transport models were used 

to study dilution characteristics of the proposed repository site for two basic purposes: (i) to 

gain insight into site specific factors that may affect groundwater mixing and attendant dilution of 

dissolved radionuclides at the Yucca Mountain site; and (ii) to determine if there are any 

methodology issues that may impact implementation of a dose or risk-based standard as 

proposed by the National Academy of Sciences. 

 
15-2 

Bagtzoglou, A.C. and M. Muller. 06/01/1994. “Stochastic Analysis of Large-Scale 

Unsaturated Flow and Transport in Layered, Heterogeneous Media.” CNWRA 94-012. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. June 1994. 

20.05704.053, Q199407050005, ML040160540 

Bagtzoglou, A.C., R. Ababou, and B. Sagar. 02/14/1992. “Effects of Layering, Dipping 

Angle, and Faulting on Two-Dimensional Variably Saturated Flow, Iterative Performance 

Assessment—Phase II.” CNWRA 92-004. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. February 1992. 

20.03702.065, Q199202210001, ML033640017 

This report documents results of unsaturated flow simulations undertaken as an auxiliary 

analysis for the Iterative Performance Assessment Phase 2 Project. The primary objective of 

the simulations is to study the effect on flow of common geological features, such as 

nonhorizontal stratification and vertical or near-vertical fault zones intersecting the strata, in a 

two-dimensional or thin “slice” domain. 

Bagtzoglou, A.C., S. Mohanty, A. Nedungadi, T.-C. Jim Yeh, and R. Ababou. 03/24/1994. 

“Effective Hydraulic Property Calculations for Unsaturated, Fractured Rock with Semi-Analytical 

and Direct Numerical Techniques: Review and Applications.” CNWRA 94-007. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. November 1994. 

20.05704.056.094.003, Q199403310005, ML033630442 

Basagaoglu, H. 06/05/2008. “Status of Colloid Release Evaluations.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. July 2008. 20.14002.01.083.840, 

Q200806050004, ML081890318 

This letter report summarizes the current Center for Nuclear Waste Regulatory Analyses 

(CNWRA) understanding of the U.S. Department of Energy (DOE) abstraction for colloidfacilitated radionuclide transport in the wasteform and engineered barrier systems. The report 

focuses on (i) type, mass concentrations, and stability of colloids; (ii) underlying assumptions of 

the abstraction and the relevant features, events, and processes; and (iii) importance of 

irreversible and reversible colloid types to radionuclide transport. 

Basagaoglu, H., S. Succi, C. Manepally, R. Fedors, and D.Y. Wyrick. “Sensitivity of the 

Active Fracture Parameter to Fracture Network Orientation and Injection Scenarios.” 

Hydrogeology Journal. Vol. 17. pp. 1,347–1,358. 2009. 

Bertetti, F.P. “Laboratory and Modeling Studies of Neptunium Uptake on Calcite.” 

CNWRA 2002-04. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

June 2002. Q200207050001, 06/26/2002, 20.01402.871.210, ML033640040 

This report summarized laboratory batch sorption experiments to evaluate neptunium 

sorption onto calcite. Results indicated that calcite was an effective sorber of neptunium. The 

results were modeled using a combination of ion exchange and surface complexation models. 

Bertetti, F.P., R.T. Pabalan, D.R. Turner, and M.G. Almendarez. “Studies of Neptunium(V) 

Sorption Onto Montmorillonite, Clinoptilolite, Quartz, and α-alumina.” Chapter 4. E. Jenne, ed. 

San Diego, California: Adsorption of Metals by Geomedia. Academic Press. pp. 131–148. 

1998. 

 
15-3 

Bertetti, F.P. and B. Werling. 09/22/2005. “Sorption of Neptunium-237 on Alluvium Collected 

from Fortymile Wash, Nye County, Nevada.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. September 2005. 

20.06002.01.242.520, Q200509220006, ML052660288 

This report provides the status and a brief summary of CNWRA experiments conducted 

to evaluate Np-237 sorption on alluvium collected from Fortymile Wash. The report includes a 

comparison of Np-237 sorption on alluvium and important single mineral phases, 

(e.g., montmorillonite) to the results of previous sorption experiments. 

Bertetti, P., R.V. Klar, and M.M. Vaught. 09/26/2006. “Colloid-Facilitated Transport of 

Radionuclides in Natural Groundwater Systems—Literature Review.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. September 2006. 

20.06002.01.242.620, Q200609260003, ML062690355 

This report discusses transport-related issues such as colloid stability, colloid retention, 

and sorption of radionuclides onto colloids, and colloid deposition and mobilization. Based on a 

review of the collected literature, several topics are identified as potential areas of detailed work 

to address uncertainties in the Yucca Mountain performance assessment abstractions of 

colloid transport. 

Bertetti, P., R. Pabalan, D. Pickett, and D. Turner. 09/06/2011. “Radionuclide Sorption 

Technical Assistance Activities at the Center for Nuclear Waste Regulatory Analyses.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.150, Q201109060004, ML112490545 

This report provides a summary of experimental, modeling, and performance 

assessment activities undertaken at CNWRA since the initial sorption projects in the late 1980s. 

Browning, L.B. and W.M. Murphy. “Reactive Transport Modeling in the Geosciences.” 

Computers and Geosciences. Vol. 29, No. 3. p. 245. April 2003. 

This short paper is a guest editorial to introduce a special issue of the journal. 

Browning, L.B., W.M. Murphy, C. Manepally, and R.W. Fedors. “Reactive Transport Model 

for the Ambient Unsaturated Hydrogeochemical System at Yucca Mountain, Nevada.” 

Computers and Geosciences. Vol. 29, No. 3. pp. 247–263. April 2003. 

The primary focus of this paper is to present a calibrated reactive transport model for the 

ambient system at Yucca Mountain, as developed from petrologic observations and 

thermodynamic and kinetic interpretations of pore water chemistry. The model predictions 

permitted evaluations of origins of dissolved silica in Yucca Mountain groundwater and 

hydrogeochemical controls on fracture and matrix groundwater compositions. 

Colton, S., A. Sun, J.A. Stamatakos, and D. Sims. 07/05/2007. “Three-Dimensional 

Hydrogeologic Model of the Amargosa Desert, Version 2.0.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. July 2007. 

20.06002.01.272.621, Q200707060003, ML071900243 

This report documents major updates and improvements made in Version 2.0 of the 

model. Version 1.0 of the model was developed by CNWRA as a conceptual framework for 

analysis of groundwater flow in the vicinity of Yucca Mountain, Nevada. Although the model 

was originally (Version 1.0) identified as Three-Dimensional Structural Model of the Amargosa 

Desert, the title was revised in Version 2.0 because the model was developed for use in 

hydrogeologic process modeling. It is more accurately described as a hydrogeologic framework 

model because the model layers are hydrogeologic units, not structural units. Version 2.0 
15-4 

incorporates newly published data and supports the independent review of the DOE site-scale, 

saturated zone flow model. 

Contardi, J.S., D.R. Turner, and T.M. Ahn. “Modeling Colloid Transport for Performance 

Assessment.” Journal of Contaminant Hydrology. Vol. 47. pp. 323–333. 2001. 

Cvetkovic, V., S.L. Painter, D.R. Turner, D.A. Pickett, and F.P. Bertetti. “Parameter and 

Model Sensitivities for Colloid-Facilitated Transport on the Field Scale.” Water Resources 

Research. Vol. 40, No. 6. June 2004. W06504, doi: 10.1029/2004WR003048. 

Farrell, D.A., V. Rankin, and A. Buseman-Williams. 10/31/2007. “Development and 

Application of Models to Simulate Saturated Zone Transport Under a Wetter Climate at 

Yucca Mountain.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

October 2007. 

20.06002.01.282.631, Q200711010001, ML073480160 

Farrell, D.A., A. Armstrong, J.R. Winterle, D.R. Turner, D.A. Ferrill, J.A. Stamatakos, 

N.M. Coleman, M.B. Gray, and S.K. Sandberg. 07/08/1999. “Structural Controls on 

Groundwater Flow in the Yucca Mountain Region.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. July 1999. 

20.01402.861.960, Q199907130002, ML033630356 

Farrell, D.A., V. Rankin, and A. Buseman-Williams. 12/07/2005. “Development and 

Application of a Model to Simulate Saturated Zone Transport From the Location of the Proposed 

Repository Footprint at Yucca Mountain.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. December 2005. 

20.06002.01.282.531, Q200512080001, ML053480229 

Fedors, R.W., J.R. Winterle, W.A. Illman, C.L. Dinwiddie, and D.L. Hughson. “Unsaturated 

Zone Flow at Yucca Mountain, Nevada: Effects of Fracture Heterogeneity and Flow in the 

Nonwelded Paintbrush Tuff Unit.” San Antonio, Texas: CNWRA. April 2002. 

20.01402.861.200, Q200204190005, ML022460157 

This report evaluates several key topics in unsaturated zone flow, including the potential 

development of preferential flow paths and the potential for lateral flow. The authors review 

recent DOE unsaturated zone flow models and present independent results from CNWRA 

modeling and field studies, particularly with respect to limited effects of lateral flow. 

Ferrill, D.A., J.R. Winterle, G.W. Wittmeyer, D.W. Sims, S. Colton, A. Armstrong, and 

A.P. Morris. “Stressed Rock Strains Groundwater at Yucca Mountain, Nevada.” GSA Today. 

Vol. 9, No. 5. pp. 1–8. 1999. 

Greathouse, J.A., G. Bemis, and R.T. Pabalan. “Molecular Dynamics Simulation of the Uranyl 

Ion Near Quartz Surfaces.” Water-Rock Interaction. R. Cidu, editor. Lisse, The Netherlands: 

A.A. Balkema Publishers. pp. 173–176. 2001. 

The effectiveness of sorption processes as a mechanism to retard radionuclide migration 

from nuclear waste repositories depends on the physicochemical characteristics of mineral 

sorbents and the chemistry of radionuclide-bearing groundwater. This paper describes the use 

of molecular simulation techniques to study the structure and dynamics of an aqueous uranium 

(VI) species, the uranyl ion, near a quartz crystallographic surface. 
15-5 

Greathouse, J.A., R.J. O'Brien, G. Bemis, and R.T. Pabalan. “Molecular Dynamics Study of 

Aqueous Uranyl Interactions with Quartz (010).” Journal of Physical Chemistry. Vol. B 106. 

pp. 1,646-1,655. 2002. 

In this study, molecular dynamics simulations were used to study the structure and 

dynamics of the uranyl ion and its aquo, hydroxy, and carbonato complexes in bulk water and 

near the hydrated quartz (010) crystallographic surface. 

Green, R.T., A.C. Bagtzoglou, G.W. Wittmeyer, B. Sagar, and R.G. Baca. 10/15/1992. 

“Computational Analysis of Groundwater Travel Time–A Preliminary Study.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. October 1992. 

20.03702.131, Q199210200001, ML033650083 

This report identifies three uncertainties related to groundwater travel time: (i) in a 

variably-saturated, fractured, layered, heterogeneous medium, it may not be possible to 

uniquely define the fastest path of radionuclide travel; (ii) the definition of disturbed zone is not 

precise; and (iii) it is not clear how much, if any, mass of water is to be associated with the flow 

tube used in computing the travel time. The report examines the need for clarification (and 

possible resolution) of the technical uncertainties associated with the geologic setting 

performance measure. 

Gureghian, A.B., Y.-T. Wu, B. Sagar, and R.B. Codell. 08/23/1991. “Sensitivity and 

Uncertainty Analyses Applied to One-Dimensional Transport in a Layered Fractured Rock, 

Part 1: Analytic Solutions and Local Sensitivities.” CNWRA 91-010. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. August 1991. 

20.03702.065, Q199109160002 ML040220140 

Also published as NUREG/CR-5917. 

Kapoor, V. 05/20/1994. “Water Film Flow in a Fracture in Unsaturated Porous Medium.” 

CNWRA 94-009. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

May 1994. 

20.05704.191, Q199405310007, ML033630684 

Lichtner, P.C. 10/24/1994. “Multi-Phase Reactive Transport Theory.” CNWRA 94-018. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. October 1994. 

20.05704.191, Q199411030002, ML040160645 

Manepally, C., K. Bradbury, S. Colton, C. Dinwiddie, R. Green, R. McGinnis, D. Sims, 

K. Smart, and G. Walter. 04/19/2007. “The Nature of Flow in the Faulted and Fractured 

Paintbrush Nonwelded Hydrogeologic Unit.” Revised. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. April 2007. 

20.06002.01.262.640, Q200704230001, ML071410138 

Manaktala, H., D. Turner, T. Ahn, V. Colten-Bradley, and E. Bonano. 09/27/1995. “Potential 

Implications of Colloids on the Long-Term Performance of a High-Level Waste Repository.” 

CNWRA 95-015. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 1995. 

20.05702.523.415, Q199704100016 ML040160817 

 
15-6 

McMurry, J. 10/31/2007. “Overview of Field and Laboratory Studies of Unsaturated Zone 

Matrix Diffusion and Related Fracture-Matrix Interactions.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses: October 2007. 

20.06002.01.232.620, Q200710310002, ML073050347 

This report provides an overview of current published research that describes field and 

laboratory studies of matrix diffusion and other examples of fracture–matrix interaction in 

unsaturated flow regimes, particularly in terms of pertinent DOE field experiments at 

Yucca Mountain. In addition to the relatively few studies that have explicitly investigated 

unsaturated zone matrix diffusion, the report summarizes other field and laboratory studies that 

have documented related unsaturated zone flow and transport processes. 

McMurry, J., and F.P. Bertetti. 12/03/2007. “Selection of Sorption-Related Values for 

Unsaturated Zone and Saturated Zone Transport in Total-System Performance Assessment.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. June 2005. 

20.06002.01.232.520, Q200712030001, ML073370866 

Mohanty, S. and S.-M. Hsiung. 09/23/2011. “An Experimental Investigation of Single Fracture 

Flow Behavior Under Normal and Shear Loads.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. September 2011. 

20.14002.01.441.155, Q201109260001, ML112690142 

Mohanty, S., A.H. Chowdhury, S.-M. Hsiung, and M.P. Ahola. 10/07/1994. “Single Fracture 

Flow Behavior of Apache Leap Tuff Under Normal and Shear Loads.” CNWRA 94-024. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. October 1994. 

20.05704.039, Q199410180001, ML040360547 

Mohanty, S., R.T. Green, and K.A. Meyers-James. 10/30/1995. “Study of Flow in a Fracture 

Under Shear: Progress Report.” CNWRA 96-001. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. October 1995. 

20.05704.039.095.005, Q199602290014, ML040330888 

Murphy, W.M. and D.A. Pickett, D.A. “Isotope Fractionation Effects on Radionuclide Transport 

in Geologic Disposal of Nuclear Waste.” Radionuclide Retention in Geologic Media. Nuclear 

Energy Agency, Organisation for Economic Co-operation and Development. p. 113–118. 2002. 

Murphy, W.M., E.C. Pearcy, R.T. Green, J.D. Prikryl, S. Mohanty, B.W. Leslie, and 

A. Nedungadi. “A Test of Long-Term, Predictive, Geochemical Transport Modeling at the 

Akrotiri Archaeological Site.” Journal of Contaminant Hydrology. Vol. 29, Issue 3. 

pp. 245–279. 1998. 

Or, D. and C. Dinwiddie. 06/28/2007. “Sensor and Measurement Considerations for 

Long-Term Hydro-Environmental Monitoring of Vadose Zone Processes.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. June 2007. 

20.06002.01.191.710, Q200706290001, ML071800385 

This report describes how long-term monitoring during performance confirmation may 

require the advancement of hydro-environmental sensor technology. Ideally, monitoring should 

include measurement redundancy (multiple sensors and methods), built-in self-calibration and 

quality assurance measures (e.g., failure detection capabilities), staged and upgradable 

monitoring network design and sensor software, and the potential for capitalization on advanced 

enabling technologies (e.g., wireless underground communication and robotic and semiautonomous monitoring and sensor-calibrating systems). 
15-7 

Or, D., M. Tuller, and S. Stothoff. 07/13/2006. Revised: “Review of Vadose Zone 

Measurement and Monitoring Tools for Yucca Mountain Performance Confirmation Program 

Performance Confirmation Program.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. July 2006. 

20.06002.01.191.610, Q200607130014, ML062060477, ML062060514, ML062060516 

This review of vadose zone monitoring methods identified shortcomings in current 

technological solutions, such that most presently available hydro-environmental sensors may 

not be suitable for long-term, deep-subsurface, fractured rock monitoring activities.

Pabalan, R.T., D.R. Turner, F.P. Bertetti, and J.D. Prikryl. “Uranium(VI) Sorption Onto 

Selected Mineral Surfaces: Key Geochemical Parameters.” Chapter 3. E. Jenne, ed. 

San Diego, California: Adsorption of Metals by Geomedia. Academic Press. pp. 99–130. 

1998. 

Pabalan, R.T. “Thermodynamics of Ion-exchange Between Clinoptilolite and Aqueous 

Solutions of Na+/K+ and Na+/Ca2+.” Geochimica et Cosmochimica Acta. Vol. 58, No. 21. 

pp. 4,573–4,590. 1994. 

To provide a thermodynamic basis for understanding zeolite-water interactions in 

geologic systems, ion-exchange experiments were conducted between clinoptilolite, which is 

the predominant zeolite mineral in altered pyroclastic and volcaniclastic rocks, and aqueous 

mixtures of Na+

/K+ and Na+/Ca2+. Isotherm points were obtained by equilibrating 

Na-clinoptilolite and chloride solutions having different ionic concentration ratios, but constant 

total normalities of 0.5, 0.05, or 0.005 N. The experimental data were interpreted using a 

Margules thermodynamic formulation for zeolite solid solutions, coupled with the Pitzer model 

for aqueous activity coefficients. The isotherm data were used to derive equilibrium constants 

and Gibbs free energies for the ion-exchange reactions. 

Pabalan, R.T. and F.P. Bertetti. “Experimental and Modeling Study of Ion Exchange Between 

Aqueous Solutions and the Zeolite Mineral Clinoptilolite.” Journal of Solution Chemistry. 

Vol. 28. pp. 367–393. 1999. 

Ion-exchange experiments were conducted between the zeolite mineral clinoptilolite and 

aqueous solutions of Na+

/Sr2+, K+/ Sr2+, and K+/Ca2+. The isotherm data were used to derive 

equilibrium constants and Gibbs energies for the ion-exchange reactions and Margules 

parameters for the zeolite solid solution. 

Pabalan, R.T. and F.P. Bertetti. “Cation-Exchange Properties of Natural Zeolites.” Reviews in 

Mineralogy and Geochemistry. Vol. 45. D. Bish and D. Ming, editors. Washington, DC: The 

Mineralogical Society of America. pp. 453–518. 2001. 

This paper summarizes information from the open literature about the cation-exchange 

properties of natural zeolites. 

Pabalan, R.T. and W.M. Murphy. 01/01/1990. “Progress in Experimental Studies on the 

Thermodynamic and Ion Exchange Properties of Clinoptilolite.” CNWRA 89-006. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. January 1990. 

20.03704.013, Q199112190005, ML040690193 

This report provides the theoretical bases for ion exchange and phase equilibrium 

studies in the Geochemistry Research Program at CNWRA, reviews experimental work reported 

in the literature on ion exchange between aqueous solutions and clinoptilolite, and presents the 

results of characterization work performed on experimental materials. The report identifies 

important factors to be considered or constrained in conducting ion exchange studies, as well as 
15-8 

procedures for ion exchange experiments that take these factors into account, and various other 

procedures relevant to the conduct of this work. 

Pabalan, R.T. and D.R. Turner. “Uranium (6+) Sorption on Montmorillonite: Experimental and 

Surface Complexation Modeling Study.” Aquatic Geochemistry. Vol. 2. pp. 203–226. 1997. 

This paper describes batch experiments that were conducted to determine the effects of 

varying pH, solid-mass to solution-volume ratio, and solution concentration on U(6+) sorption 

onto montmorillonite. The results show that U(6+) sorption on montmorillonite is a strong 

function of pH, reaching a maximum at near-neutral pH (~6 to ~6.5) and decreasing sharply 

towards more acidic or more alkaline conditions. The experimental results were used to 

develop a thermodynamic model based on a surface complexation approach to permit 

predictions of U(6+) sorption at differing physicochemical conditions. 

Painter, S. and V. Cvetkovic. 06/23/2004. “Colloid-Facilitated Transport in the Saturated 

Zone: Process-Level Sensitivity Analysis.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. June 2004. 

20.06002.01.141.430, Q200406280002, ML042160183 

Painter, S.L., V. Cvetkovic, D.A. Pickett, and D.R. Turner. “Significance of Kinetics for 

Sorption on Inorganic Colloids: Modeling and Experiment Interpretation Issues.” Environmental 

Science Technology. Vol. 36. pp. 5,369–5,375. 2002. 

This paper utilized a two-site kinetic sorption model to explore and reinterpret colloid 

sorption data derived by DOE investigators. Modeling results and sensitivity analyses 

suggested that the significance of colloid associated transport was most important for slow 

desorption rates.

Painter, S.L., V. Cvetkovic, and D.R. Turner. “Effect of Heterogeneity on Radionuclide 

Transport in the Alluvial Aquifer near Yucca Mountain, Nevada.” Groundwater. Vol. 37, No. 3. 

pp. 326–338. May 2001. 

This paper included process-level analyses to quantify the effects of physical 

heterogeneity (hydraulic conductivity) and chemical heterogeneity (Kd) on radionuclide 

retardation in the alluvial aquifer near Yucca Mountain. The hydraulic conductivity, K, was 

modeled using a unimodal lognormal distribution with exponential spatial covariance function. 

The spatial variability of Kd for Np was modeled in a similar fashion, based on a saturated zone 

geochemistry data set collected from 238 sample locations in the vicinity of Yucca Mountain. 

Uncertainty associated with mass transport was quantified using a two-site, mobile–immobile 

mass transfer model formulated in the stochastic streamtube framework, and an instantaneous 

point source was assumed. The authors concluded that the effect of physical heterogeneity is 

important; however, chemical heterogeneity and the correlation between K and Kd have minimal 

effect. They also found that treating Kd as a spatially constant but uncertain parameter greatly 

overemphasizes the effect of Kd variability. 

Painter, S.L., J.R. Winterle, and A. Armstrong. “Using Temperature to Test Models of Flow 

Near Yucca Mountain, Nevada.” Ground Water. Vol. 41, No. 5. pp. 657–666. 2003. 

Pearcy, E.C. 05/30/1994. “Fracture Transport of Uranium at the Nopal I Natural Analog Site.” 

CNWRA 94-011. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

May 1994. 

20.05704.065.094.006, Q199405310006, ML033630674 
15-9 

Pearcy, E.C., J.D. Prikryl, and B.W. Leslie. “Uranium Transport Through Fractured Silicic Tuff 

and Relative Retention in Areas with Distinct Fracture Characteristics.” Journal of Applied 

Geochemistry. Vol. 10. pp. 685–704 1995. 

Pickett, D.A. and W.L. Dam. “Approach to Assessing the Potential Effects of Colloidal 

Radionuclide Transport on Nuclear Waste Repository Performance.” Nuclear Science and 

Engineering. Vol. 151, No. 1. pp. 114–120. September 2005. 

Prikryl, J.D., A. Jain, D.R. Turner, and R.T. Pabalan. “Uranium(VI) Sorption Behavior on 

Silicate Mineral Mixtures.” Journal of Contaminant Hydrology. Vol. 47, Issues 2–4. 

pp. 241–253. February 2001. 

This paper presents the results of uranium (VI) sorption experiments involving quartz 

and clinoptilolite conducted to evaluate the ability of surface complexation models to predict 

uranium (VI) sorption onto mineral mixtures based on parameters derived from single mineral 

experiments. Data from the sorption experiments were used in a diffuse-layer surface 

complexation model (DLM) to predict sorption of uranium (VI) onto clinoptilolite/quartz mixtures. 

The DLM reproduced many aspects of the pH-dependent sorption behavior of both quartz and 

clinoptilolite. 

Prikryl, J.D., R.T. Pabalan, D.R. Turner, and B.W. Leslie. “Uranium Sorption on 

Alpha-Alumina: Effects of pH and Surface- Area/Solution-Volume Ratio.” Radiochimica Acta.

Vol. 66/67. pp. 291–296 1994. 

This paper examined the effects of solution pH and the sorbent surface area on the 

sorption behavior of uranium (VI). Experimental results indicated that uranium (VI) sorption on 

alpha-alumina occurs at near-neutral pH and increases as the sorbent-surface area/solutionvolume ratio increases. 

Prikryl, J.D., D.A. Pickett, W.M. Murphy, and E.C. Pearcy. “Migration Behavior of Naturally 

Occurring Radionuclides at the Nopal I Uranium Deposit.” Journal of Contaminant Hydrology.

Vol. 26. pp. 61–69 1997. 

This paper presents the results of petrographic, electron microprobe, and 

Uranium-series isotopic data on secondary iron-oxides/hydroxides formed in a fracture 

that crosscuts the Nopal I uranium deposit. Mobilization and transport of uranium (U) away 

from the deposit was indicated by decreasing U concentrations in fracture-filling materials and 

minerals with distance from the deposit and greater than unity 234U/238U activity ratios measured 

in fracture-filling materials.

Reeder, R.J., M. Nugent, and R.T. Pabalan. “Local Structure of Uranium (VI) Sorbed on 

Clinoptilolite and Montmorillonite.” Water-Rock Interaction. R. Cidu, editor. 

Lisse, The Netherlands: A.A. Balkema Publishers. pp. 423–426. 2001. 

In this study, X-ray absorption fine-structure (XAFS) spectroscopy was used to elucidate 

the structure of uranium (VI) sorbed onto the zeolite clinoptilolite and the clay montmorillonite. 

The solids were reacted with uranyl nitrate solutions either at pH-3.3, which favors sorption at 

fixed ion-exchange sites, or at pH -6.3, which favors sorption onto amphoteric surface hydroxyl 

sites. The results suggest that uranyl forms inner-sphere complexes with montmorillonite and 

clinoptilolite at near-neutral pH. At low pH, uranyl sorbs onto montmorillonite via an outersphere complex. Uranyl likely forms an outer-sphere complex when sorbed onto clinoptilolite at 

low pH, but steric limitations imposed by the zeolite structure probably cause the observed 

distortion of the equatorial shell. 
15-10 

Sagar, B. “Flow Modeling in Heterogeneous Media in the Context of Geologic Nuclear Waste 

Repositories.” Nuclear Science and Engineering. Vol. 123. p. 443. 1996. 

Sagar, B., A.C. Bagtzoglou, R.T. Green, and S.A. Stothoff. “Measurement and Modeling of 

Flow Through Unsaturated Heterogeneous Rock in the Context of Geologic Disposal of Nuclear 

Waste.” Heat, Mass, and Momentum Transfer in Environmental Flows. ASME. 

HTD-Vol. 321/FED-Vol. 233. pp. 271–284. 1995. 

Gureghian, A.B., Y.T. Wu, B. Sagar, and R.B. Codell. “Sensitivity and Uncertainty Analyses 

Applied to One-Dimensional Radionuclide Transport in a Layered Fractured Rock. 1. Analytical 

Solutions and Local Sensitivities.” Nuclear Technology. Vol. 104. pp. 272–296. 1993. 

Stirewalt, G.L. and D.B. Henderson. 09/28/1995. “A Three-Dimensional Geological 

Framework Model for Yucca Mountain, Nevada, with Hydrologic Application: Report to 

Accompany 1995 Model Transfer to the Nuclear Regulatory Commission, Revision 1.” 

CNWRA 94-023. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 1995. 

20.05702.425, Q199601050011, ML040220357 

Stirewalt, G.L., S.R. Young, and D. Brent Henderson. 09/29/1994. “A Preliminary 

Three-Dimensional Geological Framework Model for Yucca Mountain Nevada.” 

CNWRA 94-023. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 1994. 

20.05704.425, Q199410170002, ML040160555 

This report accompanied transfer of the three-dimensional geological framework 

modeling software to NRC. 

Sun, A.Y. 03/21/2008. “State-of-the-Art Multiscale Approaches for Flow and Transport 

Modeling: A Literature Review.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. January 2008. 

20.14002.01.131.820, Q200803240001, ML080850416 

Sun, A.Y. and P. Bertetti. 10/26/2007. “Evaluation of the Effects of Physical and Chemical 

Heterogeneities on Flow and Transport in the Saturated Alluvium of Fortymile Wash, Nevada.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. October 2007. 

20.06002.01.272.760, Q200710260001, ML073470857 

This report summarized numerical experiments conducted to quantify the effects of 

subgrid physical and chemical heterogeneities. Monte Carlo simulations were performed using 

realizations of a fine-scale block model for which the properties are generated stochastically 

based on a hierarchical alluvium facies model developed in previous work. The statistics of 

neptunium sorption parameters were derived from field data. Transport was solved in a 

Lagrangian framework in which the solute mass is divided into a large number of particles, 

which are then displaced using an efficient random walk algorithm. The results indicated that 

the upscaled block hydraulic conductivities have similar magnitudes as those assigned to the 

alluvium in site-scale models. The simulated longitudinal macrodispersivities are on the order of 

10 m [32.8 ft], depending on the variance of hydraulic conductivities. The results of reactive 

transport modeling show that retardation introduces at most a two-fold increase in solute spread 

in the longitudinal direction

 
15-11 

Sun, A.Y., R. Ritzi, and D. Sims. “Characterization and Modeling of Spatial Variability in a 

Complex Alluvial Aquifer: Implications On Solute Transport.” Water Resources Research. 

Vol. 44. 2008. doi:10.1029/2007WR006119. 

This paper modeled the sedimentary architecture of the alluvium deposits in Fortymile 

Wash, Nevada, using a hierarchical transition probability geostatistical approach. A threedimensional hierarchical hydrofacies model was developed through fusion of multiple geologic 

data types and sources. Markov chain models of transition probabilities were employed to 

represent complex patterns of spatial variability at each hierarchical level in a geostatistical 

fashion and to impose realistic constraints to such variations through conditioning on existing 

data. The link between the alluvium spatial variability and solute dispersion at different 

spatiotemporal scales was demonstrated using the stochastic-Lagrangian transport theory. The 

authors concluded that the longitudinal macrodispersivity can be on the order of hundreds to 

thousands of meters, and it may not reach its asymptotic value until after 1,000 years of travel 

time. 

Turner, D.T. 12/19/1991. “Effects of Variable Hydrologic Saturation on Sorption Modeling for 

High-Level Waste Performance Assessment: A Literature Review.” CNWRA 91-016. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. December 1991. 

20.03704.071, Q199201030004, ML003755802 

Turner, D.R. 08/01/1991. “Sorption Modeling for High-Level Waste Performance Assessment: 

A Literature Review.” CNWRA 91-011. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses: August 1991. 

20.03704.071, Q199109160004, ML040220147 

Turner, D. R. 01/12/1995. “A Uniform Approach to Surface Complexation Modeling of 

Radionuclide Sorption.” CNWRA 95-001. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. January 1995. 

20.05704.074, Q199501180001 ML040160669 

Turner, D.R. 09/01/1993. “Mechanistic Approaches to Radionuclide Sorption Modeling.” 

CNWRA 93-019. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 1993. 

20.05704.074, Q199310140033, ML040200620 

Turner, D.R. and R.T. Pabalan. “Abstraction of Mechanistic Sorption Model Results for 

Performance Assessment Calculations at Yucca Mountain, Nevada.” Waste Management. 

Vol. 19. pp. 375–388. 1999. 

Turner, D.R. and S.A. Sassman. “Approaches to Sorption Modeling for High-Level Waste 

Performance Assessment.” Journal of Contaminant Hydrology. Vol. 21. pp. 311–332. 1996. 

Turner, D.R., F.P. Bertetti, and R.T. Pabalan. “Applying Surface Complexation Modeling to 

Radionuclide Sorption.” Surface Complexation Modeling. Munich, Germany: pp. 553–604. 

September 2006. 

Turner, D.R., F.P. Bertetti, and R.T. Pabalan. “Role of Radionuclide Sorption in High-Level 

Waste Performance Assessment: Approaches for the Abstraction of Detailed Models.” 

Geochemistry of Soil Radionuclides. Soil Science Society of America Special Publication. 

Vol. 59. pp. 211–252. 2002. 
15-12 

Turner, D.R., R.T. Pabalan, and F.P. Bertetti. “Neptunium (V) Sorption on Montmorillonite: 

An Experimental and Surface Complexation Modeling Study.” Clays and Clay Minerals. 

Vol. 46. pp. 256–269. 1998.

Walter, G. 03/23/2011. Revised: “The Role of Matrix Diffusion as a Retardation and 

Attenuation Process at Yucca Mountain and Other Geologic Environments.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. March 2011. 

20.14002.01.441.114, Q201103230002, ML110820365 

Winterle, J.R. 04/16/2003. “Evaluation of Alternative Concepts for Saturated Zone Flow: 

Effects of Recharge and Water Table Rise on Flow Paths and Travel Times at Yucca Mountain.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. April 2003. 

20.06002.01.131.320, Q200304170004, ML040350576 

Winterle, J. 08/25/2005. “Simulation of Spring Flows South of Yucca Mountain, Nevada, 

Following a Potential Future Water Table Rise.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analysis. August 2005. 

20.06002.01.272.521, Q200509200002, ML052630242 

Winterle, J. and L. Gergen. 09/23/2011. “Summary of Groundwater Flow Models of the Death 

Valley Regional Aquifer System and Yucca Mountain Area.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses: September 2011. 

20.14002.01.441.152, Q201109230004, ML112660339 

Winterle, J.R., R.W. Fedors, D.L. Hughson, and S.A. Stothoff. 02/25/1999. “Review of 

the Unsaturated Zone Models Used to Support the Viability Assessment of a Repository at 

Yucca Mountain.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

February 1999. 

20.01402.861.930, Q199903030004, ML033630074 

Wittmeyer, G.W. and D.R. Turner. 09/27/1995. “Conceptual and Mathematical Models of the 

Death Valley Regional Groundwater Flow System.” CNWRA 95-019. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. September 1995. 

20.05704.132, Q199601050015, ML040220379 

Wu, Y.-T., A.B. Gureghian, and B. Sagar. 03/12/1992. “Sensitivity and Uncertainty Analyses 

Applied to One-Dimensional Transport in a Layered, Fractured Rock. Part 2: Evaluation of 

Limit State Approach, Iterative Performance Assessment—Phase II.” CNWRA 92-002. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. March 1992. 

20.03702.065, Q199203180005, ML040330673 

Zaidan, O.F., J.A. Greathouse, and R.T. Pabalan. “Monte Carlo and Molecular Dynamics 

Simulation of Uranyl Adsorption on Montmorillonite Clay.” Clays and Clay Minerals. Vol. 51. 

pp. 372–381. 2003. 

In this study, Monte Carlo and molecular dynamics simulations were conducted to 

investigate the interlayer structure of a uranyl-substituted smectite clay.
16-1 

16 AQUEOUS AND VOLCANIC DOSE (BIOSPHERE) 

The main biosphere dose pathways of interest in Yucca Mountain studies were those resulting 

from radionuclides released to the surface environment from groundwater and from volcanic 

ash (tephra). 

Benke, R. and D. Hooper. 09/02/2011. “Airborne Particle Resuspension and Inhalation 

Radiological Dose Estimation Following Volcanic Events.” San Antonio, Texas: Center for 

Nuclear Waste Regulatory Analyses. September 2011. 

20.14002.01.441.142, Q201109020013, ML112450435 

For extrusive volcanism at a geologic repository, the inhalation of resuspended 

radionuclides is expected to dominate other potential exposure pathways in long-term 

performance assessments. The purpose of this knowledge management report is to describe, 

in a single document, the concepts and factors that influence the radiological dose calculation 

for the inhalation of resuspended particles contaminated with high-level waste. 

Benke, R.R., D.M. Hooper, J.S. Durham, D.R. Bannon, K.L. Compton, M. Necsoiu, and 

R.N. McGinnis. “Measurement of Airborne Particle Concentrations Near the Sunset Crater 

Volcano, Arizona.” Health Physics. Vol. 96, Issue 2. pp. 97–117. 2009. 

Airborne particle mass concentrations were measured using a personal sampler under a 

variety of surface-disturbing activities within different depositional environments at both volcanic 

and nonvolcanic sites near the Sunset Crater volcano in northern Arizona. The level of 

surface-disturbing activity was found to be the most influential factor affecting the measured 

airborne particle concentrations, which increased over three orders of magnitude relative to 

ambient conditions. Overall, the ground surface material type, depositional environment, and 

percentage of near-surface mass that is resuspendible were not as influential as other factors. 

Deere, L. and P. LaPlante. 02/03/1999. “(1) Viability Assessment Review: Location and 

Lifestyle of Critical Group KESA and (2) Dilution of Radionuclides in Soil KESA.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. 1999. 

20.01403.771.910, Q199905050018, ML033640472

Hooper, D.M. 10/17/2005. “Modeling the Long -Term Fluvial Redistribution of Tephra in 

Fortymile Wash, Yucca Mountain, Nevada.” Revised. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. July 2005. 

20.06002.01.362.530, Q200510180001, ML052910334 

This report communicates the current understanding of tephra redistribution analyses 

independently developed by Center for Nuclear Waste Regulatory Analyses (CNWRA) staff. 

The report describes a sediment budget approach to analyze the potential posteruption 

redistribution of tephra in the Fortymile Wash drainage system at Yucca Mountain, Nevada. 

Fortymile Wash is an ephemeral stream; hydrologic data are minimal, and sediment transport 

data are lacking. Rates of erosion in arid regions are not well-constrained, but a suitable range 

of values can be entered into a sediment budget to demonstrate the quantitative or mass flux 

relationship between such components as sediment yield, discharge to the depositional fan, 

balance of remaining tephra, dilution by mixing with ambient sediment, and associated changes 

in transient sediment storage. 

 
16-2 

Hooper, D.M. 03/17/2004. “First-Order Conceptual Model for Fluvial Remobilization of Tephra 

Along Fortymile Wash, Yucca Mountain, Nevada.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. February 2004. 

20.06002.01.051.465, Q200403220009, ML041320668 

This report described a first-order conceptual model that focuses on a simplified 

mass-balance approach to analyze the remobilization or redistribution of tephra in the 

Fortymile Wash drainage system at Yucca Mountain, Nevada. The methodology is first tested 

by applying it to the tephra deposit from the 1943–1952 eruption of Parícutin volcano (Mexico), 

the primary analog for this study. Erosional processes are mostly simplified in this first-order 

approach, but model refinements are incorporated. Results for the Fortymile Wash watershed 

are dependent upon the erosion rate as well as the area, thickness, and volume of dispersed 

tephra within the watershed. 

Hooper, D.M., M. Necsoiu, and R.R. Benke. 02/27/2008. “Final Status Report of Field 

Observations From Sunset Crater, Arizona.” San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. February 2008. 

20.06002.01.312.640, Q200802270003, ML080720613 (Part 1), ML080720615 (Part 2) 

This report summarizes CNWRA field activities conducted at Sunset Crater, Arizona. 

Because Sunset Crater volcano is a relatively young basaltic cinder cone that now exists in the 

semi-arid climate of Northern Arizona, it is used as an analog for future basaltic volcanism at 

Yucca Mountain. The work at Sunset Crater thus provides staff with important constraints on 

the surficial geologic processes that control redistribution of ash and tephra following 

an eruption. 

Jarzemba, M.S. 09/28/1995. “Stochastic Radionuclide Distribution After a Basaltic Eruption for 

Performance Assessment of Yucca Mountain.” Nuclear Technology. Vol. 118. pp. 132–141. 

1995. 

The paper describes a stochastic modeling approach for simulating the airborne release 

of radioactive particulates associated with a volcanism scenario. The modeling approach 

considers such factors as the eruption energetics, eruption duration, wind velocity, and particle 

properties to compute the activity areal density of particles as a function of spatial location. 

Various components of the model are based on empirical relationships and data report in the 

volcanology literature. Illustrative applications of the stochastic model are presented for the 

cases of single and multiple event eruptions. 

Jarzemba, M.S. and P.A. LaPlante. 05/14/1996. “Preliminary Calculations of Expected Dose 

from Extrusive Volcanic Events at Yucca Mountain.” San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. May 1996. 

20.05708.771.610, Q199606140002 ML040220041 

This report, which was prepared in consideration of the revision of the U.S. 

Environmental Protection Agency standard, describes a set of scoping calculations: 

(i) volcanism scenario,(ii) hazards comparison, and (iii) plume dilution. 

LaPlante, P. 08/29/2006. “Preliminary Description of Abstracted Models for Biosphere 

Pathways and Dose in the Total-System Performance Assessment (TPA) Version 5.1 Beta 

Code.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 2006. 

20.06002.01.372.630, Q200608290007, ML062420097 

 
16-3 

LaPlante, P.A. and K. Poor. 07/25/1997. “Information and Analyses to Support Selection of 

Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios.” 

CNWRA 97-009. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

August 1997. 

20.05708.761, Q199709240001, ML040200056 

This report provides updated dose conversion factors, summarizes and documents the 

site-specific characteristics and parameters used in modeling the environmental pathways, and 

presents the results of a sensitivity analysis to identify the model parameters that have the 

greatest effect on the dose calculations. 

LaPlante, P.A., M.S. Jarzemba, R.B. Neel, and C.A. McKenney. 06/10/1996. “An Initial 

Approach for Defining Potential Site-Specific Reference Biospheres and Critical Groups for 

Exposure Scenarios. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

June 1996. 

20.05708.771.620, Q199607160008 ML040230619 

LaPlante, P.A., S.J. Maheras, and M.S. Jarzemba. 10/02/1995. “Initial Analysis of Selected 

Site-Specific Dose Assessment Parameters and Exposure Pathways Applicable to a 

Groundwater Release Scenario at Yucca Mountain.” CNWRA 95-018. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. September 1995. 

20.05702.723.602, Q199602290017, ML040330891 
17-1 

17 SPECIAL PROJECTS 

17.1 Aluminum-Based Fuel Characteristics 

Brossia, S.C. 09/08/1999. “Review of the U.S. Department of Energy Evaluation of the 

Disposability of Aluminum-Based Spent Nuclear Fuel Final Report.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. September 1999. 

20.01407.001.930, Q200310010002, ML040350730

Chowdhury, D. Deere, V. Jain, D. Pickett, N. Sridhar, and J. Weldy. 05/29/1998. “Review of 

the Technical Issues Related to Interim Storage and Disposal of Aluminum Based Spent 

Nuclear Fuel.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

May 1998. 

20.01407.001.810, Q199806050001, ML033640251 

Weldy, J., D. Pickett, N. Sridhar, and S. Brossia. 03/29/1999. “Evaluation of the 

U.S. Department of Energy Aluminum-Based Fuel Criticality Analyses.” San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. 1999. 

20.01407.001.905, Q200309300040, ML040350722 

17.2 West Valley 

Cragnolino, G.A. 04/29/1993. “Review of Corrosion Aspects of High-Level Waste Storage 

Tanks at West Valley.” CNWRA 93-008. San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. April 1993. 

20.05706.004, Q199305030002, ML033630389 

Cragnolino, G.A. 09/23/1994. “Review of the West Valley THOREX Waste Neutralization 

Process.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. September 

1994. 

20.05706.003.100, Q199410140004, ML040230579 

Pomerening, D.J., C. Tschoepe, and P.K. Nair. 04/29/1993. “Seismic/Tornado Analysis 

Review for the Vitrification Facility at West Valley.” CNWRA 93-007. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. April 1993. 

20.05706.003, Q199305030003, ML040200332 

Tschoepe, E. 01/17/1995. “Report on Vitrification Operations Readiness Review—Waste 

Solidification Systems.” San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

1995. 

20.05706.001.600, Q199705310005, ML040200115 

Tschoepe, E., P.C. Mackin, D.J. Pomerening, D.J. Stevens, D.E. Ketchum, H. Manaktala, 

H. Karimi, P.J. Mayo, and D. Williams. 08/27/1996. “Review of Draft Environmental Impact 

Statement for Completion of the West Valley Demonstration Project and Closure or Long-Term 

Management of Facilities at the Western New York Nuclear Service Center.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. August 1996. 

20.05706.003.605, Q199610140002, ML040230632 

 
17-2 

Tschoepe, E., D.J. Pomerening, and P.K. Nair. 04/14/1995. “Draft Safety Evaluation Report 

on the Vitrification Process and High-Level Waste Interim Storage, Review of WVNS-SAR-003.” 

Rev. 2, Draft D. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

April 1995. 

20.05706.002, Q199506070001, ML040220304 

17.3 Hanford Tank Waste Project 

Cragnolino, G.A., M.S. Jarzemba, J. Ledbetter-Ferrill, W.M. Murphy, R.T. Pabalan, 

D.A. Pickett, J.D. Prikryl, and N. Sridhar. 07/24/1997. “Hanford Tank Waste Remediation 

System Familiarization Report.” CNWRA 97-001. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. Revised July 1997. 

20.05709.101.730, Q199709030018, ML040200047 

This is the final version of a report that summarizes a large volume of information 

available regarding the Hanford site, tank farms, and activities pertaining to the Tank Waste 

Remediation System (TWRS). The report includes a description of tank waste contents, types 

of hazards posed by the tanks and TWRS activities. See Sridhar, et al., December 1996–April 

1997, in this bibliography for references to detailed earlier parts of this report.

Deere, L. and P. LaPlante. 02/03/1999. “(1) Viability Assessment Review: Location and 

Lifestyle of Critical Group KESA and (2) Dilution of Radionuclides in Soil KESA.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. 1999. 

20.01403.771.910, Q199905050018, ML033640472 

Frank, M. 09/16/1998. “A Survey of Risk Assessment Methods from the Nuclear, Chemical, 

and Aerospace Industries for Applicability to the Privatized Vitrification of Hanford Tank Waste.” 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. August 1998. 

20.01403.103.810, Q199809090002, ML033640266 

Jain, V. 04/24/1998. “Survey of Solidification Process Technologies.” CNWRA 98-005. 

San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. April 1998. 

20.01403.102.810, Q199805050002, ML033640242 

Jain, V. 10/16/2000. “Chemical Durability of Nuclear Waste Glasses–A Review.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. 2000. 

(Manuscript prepared for Journal of Materials Science & Technology) 

20.01403.106, Q200310010001, ML061310303 

Jain, V. 03/23/1999. “Radioactive Waste Treatment/Nuclear Material Production Facility 

Integrated Design Inspection Program” “San Antonio, Texas: Center for Nuclear Waste 

Regulatory Analyses. 1999. 

20.01403.202.930, Q200310020001, ML040350737 

This document describes an inspection program methodology to be used for performing 

multidisciplinary integrated design inspections at radioactive waste treatment and nuclear 

material processing plants. 

Jain, V. 05/29/1997. “Survey of Solidification Process Technologies–Interim Report.” 

CNWRA 97-005. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

May 1997–August 1997. 

20.05709.102.710, Q199710300016, ML040780182 
17-3 

Jain, V. and Y.-M. Pan. 09/01/2000. “Glass Melt Chemistry and Product Qualification.” 

CNWRA 2000-05. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses. 

September 2000. 

20.01403.106.030, Q200012270001 ML033640523 

Pabalan, R.T., M.S. Jarzemba, T.A. Abrajano, Jr., D.A. Pickett, D. S. Moulton, N. Sridhar, 

J. Weldy, C.S. Brazel, J.T. Persyn, B. Li, J.P. Hsu, and J. Erwin. . “High Level Waste 

Chemistry Manual.” CNWRA 97-008. Revision 1. San Antonio, Texas: Center for Nuclear 

Waste Regulatory Analyses. June 1998. 

20.05708.106.705, Q199709030017, ML033640258. 

Pabalan, R.T., V. Jain, R.F. Vance, S. Ioannidis, D.A. Pickett, C.S. Brazel, J.T. Persyn, 

E. Jennings Taylor, and M.E. Innman. 12/14/2000. NUREG/CR-6714, “Hanford Tank Waste 

Remediation System Pretreatment Chemistry and Technology.” September 2001. 

20.01403.106.020, Q200012180003, ML012690529 

Pickett, D. and R. Fedors. 03/05/1999. “Review of the Hanford Immobilized Low-Activity Tank 

Waste Performance Assessment.” San Antonio, Texas: Center for Nuclear Waste Regulatory 

Analyses. March 1999. 

20.01403.201.930, Q199903090002, ML033640464 

Sridhar, N., R.T. Pabalan, M.S. Jarzemba, and W.M. Murphy. 12/17/1996. “Hanford Tank 

Waste Remediation System Familiarization Report.” CNWRA 97-001. San Antonio, Texas: 

Center for Nuclear Waste Regulatory Analyses. December 1996–April 1997. 

20.05709.101.710, Q199705310007, ML040200118, ML040200138, ML040200141 

This report, published in several parts, summarizes the large volume of information 

available regarding the Hanford site, tank farms, and ongoing activities pertaining to the Tank 

Waste Remediation System (TWRS). The report includes a description of tank waste contents, 

types of hazards posed by the tanks and TWRS activities. 

Yang, L. and R.T. Pabalan. 02/24/2000. “PRETREAT: A Spreadsheet-Based Mass-Balance 

Model for Hanford Tank Waste Remediation System Pretreatment Processes.” San Antonio, 

Texas: Center for Nuclear Waste Regulatory Analyses. August 2000. 

20.01403.106.010, Q200008290005, ML033640503 
APPENDIX 

CNWRA-SERIES REPORTS: 1988–2008 
A–1 

APPENDIX 

CNWRA-Series Reports: 1988–2008 

The first bound and numbered CNWRA-series reports were issued in 1988, soon after the 

Center for Nuclear Waste Regulatory Analyses (CNWRA®) was established. With few 

exceptions, the CNWRA reports between 1988 and 2008 dealt with high-level nuclear waste 

management topics, with a particular focus on technical and programmatic issues for evaluating 

the safety of a proposed geologic repository at Yucca Mountain, Nevada. For completeness, all 

numbered CNWRA reports that were published between 1988 and 2008 (including technical, 

planning, and quality assurance topics) are listed here. Where available, accession numbers 

are provided for those CNWRA documents that are publicly available for viewing in the 

U.S. Nuclear Regulatory Commission (NRC) Agencywide Document Access and Management 

System (ADAMS). 

When the U.S. Department of Energy submitted a license application for a geologic repository at 

Yucca Mountain in mid-2008, CNWRA technical activities transitioned from pre-licensing to 

license review support for NRC. No CNWRA-series reports specific to the Yucca Mountain 

activities were issued after 2008. 

2008 

CNWRA 2008-001 

Infiltration Tabulator for Yucca Mountain: Bases and Confirmation 

Stothoff, S. 

August 2008 

ML082350701 

2007 

CNWRA 2007-003 

Long-Term Average Infiltration at Yucca Mountain, Nevada: Million-Year Estimates 

Stothoff, S. and G. Walter 

August 2007 

ML072760607 

CNWRA 2007-002 

Literature Review and Analysis: Climate and Infiltration 

Stothoff, S. and M. Musgrove 

November 2006 

ML063190115 

CNWRA 2007-01 

Stress Corrosion Cracking for Waste Package Materials—Modeling and Experiments 

Chiang, K.-T., D.S. Dunn, Y.-M. Pan, O. Pensado, and P.K. Shukla 

December 2006 

ML070030061 
A–2 

2006 

CNWRA 2006-02 (Revision 1) 

Summary of Current Understanding of Drift Degradation and Its Effects on Performance at a 

Potential Yucca Mountain Repository 

Ofoegbu, G., R. Fedors, C. Grossman, S. Hsiung, L. Ibarra, C. Manepally, J. Myers, M. Nataraja, 

O. Pensado, K. Smart, and D. Wyrick 

April 2007 

ML070650462 

CNWRA 2006-001 

Crevice Corrosion Penetration Rate of Alloy 22 in Chloride-Containing Waters 

He, X. and D.S. Dunn 

December 2005 

ML062440377 

2005 

CNWRA 2005-04 

Summary and Analysis of Subsurface Fracture Data From the Topopah Spring Tuff Upper 

Lithophysal, Middle Nonlithophysal, Lower Lithophysal, and Lower Nonlithophysal Zones at 

Yucca Mountain, Nevada 

Smart, K.J., D.Y. Wyrick, P.S. Landis, and D.J. Waiting 

March 2006 

ML060660009 

CNWRA 2005-03 

Microstructural Analyses and Mechanical Properties of Alloy 22

Dunn, D.S., Y.-M. Pan, and K.T. Chiang 

March 2005 

ML050910074 

CNWRA 2005-02 (Revision 1) 

Passive and Localized Corrosion of Alloy 22—Modeling and Experiments 

Dunn, D.S., O. Pensado, Y.-M. Pan, R.T. Pabalan, L. Yang, X. He, and K.T. Chiang 

December 2005 

ML071560057 

CNWRA 2005-01 

Microbially Influenced Corrosion Studies of Engineered Barrier System Materials 

Yang, L., S. Birnbaum, and G.A. Cragnolino 

October 2004 

2004 

CNWRA 2004-09 (Revision 1) 

Comments on Selected Sections of Nagra Safety Case Documents NTB 02-05 and Supporting 

Documents—Final Report 

Jain, V., G. Cragnolino, and D. Dunn 

November 2004 

 
A–3 

CNWRA 2004-08 

A Review Report on High Burnup Spent Nuclear Fuel—Disposal Issues 

Jain, V., G. Cragnolino, and L. Howard 

September 2004 

ML043020321 

CNWRA 2004-07 

Chemical Speciation, Using Thermodynamic Modeling, During A Representative Loss-of-Coolant 

Accident Event 

Jain, V., L. Yang, and K. Chiang 

July 2004 

CNWRA 2004-06 

Performance Confirmation Activities Under 10 CFR Part 63 With Emphasis on Activities 

Potentially Significant to Waste Isolation 

Pabalan, R., P. Bertetti, G. Cragnolino, C. Dinwiddie, R. Fedors, B. Hill, V. Jain, G. Ofoegbu, Y.-M. Pan, 

E. Pearcy, R. Read, K. Smart, G. Walter, and J. Winterle 

September 2004 

CNWRA 2004-05 

Drift-Scale Thermohydrological Process Modeling—In-Drift Heat Transfer and Drift Degradation 

Manepally, C., A. Sun, R. Fedors, and D. Farrell 

July 2004 

ML042160447 

CNWRA 2004-04 

Temperature and Relative Humidity Along Heated Drifts With and Without Drift Degradation 

Fedors, R., S. Green, D. Walter, G. Adams, D. Farrell, and S. Svedeman 

June 2004 

ML042160472 

CNWRA 2004-03 

Effect of Fabrication Processes on The Mechanical Properties of Waste Packages 

Dunn, D., Y.-M. Pan , D. Daruwalla, and A. Csontos 

July 2004 

ML042960436 

CNWRA 2004-02 

Natural Analogs of High-Level Container Materials—Experimental Evaluation of Josephinite 

Cragnolino, G.A., Y.-M. Pan, D. Turner, and E. Pearcy 

January 2004 

ML041390323 

CNWRA 2004-01 

Effect of Fabrication Processes on Material Stability—Characterization and Corrosion 

Dunn, D., D. Daruwalla, and Y.-M. Pan 

October 2003 

ML040480532 

 
A–4 

2003 

CNWRA 2003-06 

Mechfail: A Total-System Performance Assessment Code Module for Evaluating Engineered 

Barrier Performance Under Mechanical Loading Conditions 

Gute, G.D., G. Ofoegbu, F. Thomassy, S.-M. Hsiung, G. Adams, A. Ghosh, B. Dasgupta, 

A.H. Chowdhury, and S. Mohanty 

May 2003 

ML040350587 

CNWRA 2003-05 

Assessment of Mechanisms for Early Waste Package Failures 

Jain, V., D. Daruwalla, and C. Fairbanks 

March 2003 

ML040350562 

CNWRA 2003-04 (Revision 1) 

Analysis of Rail Car Components Exposed to a Tunnel Fire Environment 

Garabedian, A.S., D.S. Dunn, and A.H. Chowdhury 

March 2003 

ML033640190 

CNWRA 2003-03 

Dynamic Soil-Structure Interaction Analysis of a Storage-Cask Foundation Design 

Ofoegbu, G.I. and G.D. Gute 

October 2002 

ML033640101 

CNWRA 2003-02 

Stress Corrosion Cracking and Hydrogen Embrittlement of Container and Drip Shield Materials 

Pan, Y.-M., C.S. Brossia, G.A. Cragnolino, D.S. Dunn, G.D. Gute, and L. Yang 

October 2002 

ML033640096 

CNWRA 2003-01 

Passive Dissolution of Container Materials—Modeling and Experiments 

Pensado, O., D.S. Dunn, G.A. Cragnolino, and V. Jain 

October 2002 

ML033640090 

2002 

CNWRA 2002-05 (Revision 2) 

System-Level Performance Assessment of the Proposed Repository at Yucca Mountain Using the 

TPA Version 4.1 Code 

Mohanty, S., R. Codell, J.M. Menchaca, R. Janetzke, M. Smith, P. LaPlante, M. Rahimi, and A. Lozano 

March 2004 

ML041350316 

CNWRA 2002-04 

Laboratory and Modeling Studies of Neptunium Uptake on Calcite 

Bertetti, F.P. 

June 2002 

ML033640040 
A–5 

CNWRA 2002-03 

Effect of Salt Formation on the Chemical Environment of Drip Shields and Waste Packages at the 

Proposed Nuclear Waste Repository at Yucca Mountain, Nevada 

Pabalan, R.T., L. Yang, and L.B. Browning 

May 2002 

ML021680067 

CNWRA 2002-02 

Evaluation of Analogs for the Performance Assessment of High-Level Waste Container Materials 

Sridhar, N. and G. Cragnolino 

March 2002 

ML033630367 

CNWRA 2002-01 

Effect of In-Package Chemistry on the Degradation of Vitrified High-Level Radioactive Waste and 

Spent Nuclear Fuel Cladding 

Pan, Y.-M., C.S. Brossia, G.A. Cragnolino, V. Jain, O. Pensado, and N. Sridhar 

October 2001 

ML033630347 

2001 

CNWRA 2001-03 

Effect of In-Package Chemistry on the Degradation of Vitrified High-Level Radioactive Waste and 

Spent Nuclear Fuel Cladding 

Brossia, C.W., L. Browning, D.S. Dunn, O.C. Moghissi, O. Pensado, and L. Yang 

September 2001 

ML020230189 

CNWRA 2001-02 (Revision 1) 

Response to the External Peer Review of the Total-System Performance Assessment Version 3.2 

Code 

Weldy, J. and J. Peckenpaugh 

February 2003 

ML031681060 

CNWRA 2001-01 (Revision 1) 

Review and Evaluation of Site Characteristics of Naval Reactors Spent Fuel ISFSI Site at INEEL 

Stamatakos, J., S.-M. Hsiung, A.H. Chowdhury, M.P. Miklas, R.T. Green, and C.B. Connor 

January 2001 

ML033640226 

2000 

CNWRA 2000-06 (Revision 1) 

Assessment of Methodologies to Confirm Container Performance Model Predictions 

Brossia, C.W., D.S. Dunn, O.C. Moghissi, and N. Sridhar 

January 2001 

ML033640217 

CNWRA 2000-05 

Glass Melt Chemistry and Product Qualification 

Jain, V. and Y.-M. Pan 

September 2000 

ML033640523 
A–6 

CNWRA 2000-04 

Drift Stability and Ground Support Performance Under Thermal and Dynamic Load in Fractured 

Rock Mass at Yucca Mountain, Nevada 

Chen, R. 

July 2000 

ML012970227 

CNWRA 2000-03 

Thermal-Mechanical Effects on Long-Term Hydrological Properties at the Proposed Yucca 

Mountain Nuclear Waste Repository 

Ofoegbu, G. 

June 2000 

ML043440528 

CNWRA 2000-02 

PVHA_YM Version 1.0—Probabilistic Volcanic Hazard Assessment Methods for a Proposed 

High-Level Radioactive Waste Repository at Yucca Mountain, Nevada 

McKague, H.L. 

February 2000 

ML033630410 

CNWRA 2000-01 (Revision 1) 

External Peer Review of the Total-System Performance Assessment Version 3.2 Code

Weldy, J.R., G.W. Wittmeyer, and D.R. Turner 

February 2000 

ML033630329 

1999 

CNWRA 1999-004 

Effects of Environmental Factors on the Aqueous Corrosion of High-Level Radioactive Waste 

Containers—Experimental Results and Models 

Dunn, D.S., Y.-M. Pan, and G.A. Cragnolino 

September 1999 

ML043150059 

CNWRA 1999-003 

Assessment of Performance Issues Related to Alternate Engineered Barrier System Materials and 

Design Options 

Cragnolino, G.A., D.S. Dunn, C.S. Brossia, V. Jain, and K.S. Chan 

September 1999 

ML033630295 

CNWRA 1999-002 

System-Level Repository Sensitivity Analyses Using TPA Version 3.2 Code 

Mohanty, S., R. Codell, R.W. Rice, J. Weldy, Y. Lu, R.M. Byrne, T.J. McCartin, M.S. Jarzemba, and 

G. Wittmeyer 

August 1999 

ML040780203 

CNWRA 1999-001 (Revision 1.1) 

Review of British Nuclear Fuels Limited (BNFL) Inc. Design Safety Features Deliverable: Hydrogen 

Control in High-Level Waste Storage Tanks 

Jain, V., R. Pabalan, D. Daruwalla, J. Weldy, and D. Pickett 

April 1999 
A–7 

1998 

CNWRA 1998-008 

Effects of Environmental Factors on Container Life 

Brossia, S., D. Dunn, and N. Sridhar 

July 1998 

ML032940364 

CNWRA 1998-007 

Seismic Ground Motion at Three Mile Island Unit 2 Independent Spent Fuel 

Storage Installation Site in Idaho National Engineering and Environmental 

Laboratory—Final Report 

Chowdhury, A. and R. Chen 

June 1998 

ML040780189 

CNWRA 1998-006 

(unidentified) 

CNWRA 1998-005 

NUREG/CR-6666: Survey of Solidification Process Technologies 

Jain, V. 

January 2000 

ML033640242 

CNWRA 1998-004 

Effect of Galvanic Coupling Between Overpack Materials of High-Level Nuclear Waste 

Containers—Experimental and Modeling Results 

Dunn, D. and G.A. Cragnolino 

March 1998 

ML032890357 

CNWRA 1998-003 

Analysis of 10 CFR Part 72 Adequacy for Licensing Storage of Three Mile Island Unit 2 Spent 

Fuel—Final Report 

Mackin, P.C. 

November 1997 

CNWRA 1998-002 

Characteristics of the Three Mile Island Unit 2 Fuel Debris—Final Report 

Cragnolino, G.A. 

November 1997 

CNWRA 1998-001 

Ground Magnetic Surveys in the Yucca Mountain Region, Nevada (1996-1997) 

Magsino, S.C., C.B. Connor, B.E. Hill, J.A. Stamatakos, P.C. LaFemina, D.A. Sims, and 

R.H. Martin 

January 1998 

ML032890330 

 
A–8 

1997 

CNWRA 1997-010 

An Analysis of Galvanic Coupling Effects on the Performance of High-Level Waste Container 

Materials 

Dunn, D.S. and G.A. Cragnolino 

August 1997 

ML040200062 

CNWRA 1997-009 

Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for 

Yucca Mountain Exposure Scenarios 

LaPlante, P.A. and K. Poor 

August 1997 

ML040200056 

CNWRA 1997-008 (Revision 1) 

Hanford Tank Waste Remediation System High-Level Waste Chemistry Manual 

Pabalan, R.T., M.S. Jarzemba, T.A. Abrajano Jr., D.A. Pickett, D.S. Moulton, N. Sridhar, J. Weldy, 

C.S. Brazel, J.T. Persyn, B. Li, J.P. Hsu, and J.l Erwin 

June 1998 

ML033640258 

CNWRA 1997-007 

A Parametric Study of Drift Stability in Jointed Rock Mass - Phase II: Discrete Element Dynamic 

Analysis of Unbackfilled Drifts 

Ahola, M.A. 

June 1997 

ML040200090 

CNWRA 1997-006 

Engineered Barrier System Performance Assessment Code: EBSPAC Version 1.1: Technical 

Description and User's Manual 

Mohanty, S., G.A. Cragnolino, T. Ahn, D.S. Dunn, P.C. Lichtner, R.D. Manteufel, and 

N. Sridhar 

June 1997 

CNWRA 1997-005 

Survey of Solidification Process Technologies—Interim Report 

Jain, V. 

May 1997 

ML040780182 

CNWRA 1997-004 (Revision 1) 

Ashplume Version 1.0—A Code for Contaminated Ash Dispersal and 

Deposition—Technical Description and User's Guide 

Jarzemba, M.S., P.A. La Plante, and K.J. Poor 

June 1997 

ML040200069 

 
A–9 

CNWRA 1997-003 

Review of Low-Temperature Oxidation of Carbon Steels and Low-Alloy Steels for Use as 

High-Level Radioactive Waste Package Materials 

Larose, S. and R.A. Rapp 

February 1997 

ML040200112 

CNWRA 1997-002 

Faulting Version 1.0—A Code for Simulation of Direct Fault Disruption—Technical Description and 

User's Guide 

Ghosh, A., R.D. Manteufel, and G.L. Stirewalt 

ML040160867 

CNWRA 1997-001 (Revision) 

Hanford Tank Waste Remediation System Familiarization Report (December 1996 to April 1997) 

Cragnolino, G.A., M.S. Jarzemba, J. Ledbetter-Ferrill, W.M. Murphy, R.T. Pabalan, D.A. Pickett, J.D. 

Prikryl, and N. Sridhar 

July 1997 

ML040200047 

1996 

CNWRA 1996-011 

Engineered Barrier System Performance Assessment Code: EBSPAC 

Version 1.0B—Technical Description and User's Manual 

Mohanty, S., G.A. Cragnolino, T. Ahn, D.S. Dunn, P.C. Lichtner, R.D. Manteufel, and N. Sridhar 

September 1996 

ML040160812 

CNWRA 1996-010 

User's Manual for MULTIFLO: Part II—MULTIFLO 1.0 and GEM 1.0 Multicomponent-Multiphase 

Reactive Transport Model 

Lichtner, P.C. and M.S. Seth 

September 1996 

ML040160828 

CNWRA 1996-009 

A Parametric Study of Drift Stability in Jointed Rock Mass—Phase 1: Discrete Element 

Thermal-Mechanical Analysis of Unbackfilled Drifts 

Ahola, M.P., R. Chen, H. Karimi, S. Hsiung, and A.H. Chowdhury 

September 1996 

ML040230678 

CNWRA 1996-008 

(unidentified) 

CNWRA 1996-007 (Revision 1) 

Type I Faults In The Yucca Mountain Region 

McKague, H.L., J.A. Stamatakos, and D.A. Ferrill 

November 1996 

ML040220051 

CNWRA 1996-006 

(unidentified) 
A–10 

CNWRA 1996-005 

User's Manual for MULTIFLO: Part 1, Metra 1.0B Two-Phase Nonisothermal Flow Simulator 

Seth, M.A. and P.C. Lichtner 

ML040230606 

CNWRA 1996-004 

Thermal Stability and Mechanical Properties of High-Level Radioactive Waste Container Materials: 

Assessment of Carbon and Low-Alloy Steels 

Cragnolino, G.A., H.K. Manaktala, and Y.-M Pan 

May 1996 

ML040230612 

CNWRA 1996-003 

Benchmark Testing of Thermohydrologic Computer Codes 

Baca, R.G. and M.S. Seth 

February 1996 

ML040220029 

CNWRA 1996-002 

Ground Magnetic Survey of the Little Cones, Crater Flat, Nevada 

Connor, C.B., R.H. Martin, P.G. Hunka, J.A. Stamatakos, D.B. Henderson, and 

R.V. Klar 

November 1995 

ML040220433 

CNWRA 1996-001A 

NRC High-Level Radioactive Waste Program Annual Progress Report Fiscal Year 1996 er 2) 

Ahn, T., R. Bradbury, R. Codell, N. Coleman, B. Jagannath, R. Johnson, P. Justus, M. Lee, B. Leslie, 

T. McCartin, M. Nataraja, J. Trapp, R. Wescott, P. Angell, R. Baca, A. Bagtzoglou, R. Chen, A. 

Chowdhury, C. Connor, G. Cragnolino, A. DeWispelare, D. Dunn, D. Ferrill, A. Ghosh, R. Green, B. Hill, 

S. Hsiung, M. Jarzemba, P. Lichtner, P. Mackin, S. Mohanty, W. Murphy, G. Ofoebgu, R. Pabalan, 

E. Pearcy, D. Pickett, B. Sagar, N. Sridhar, J. Stamatakos, S. Stothoff, D. Turner, and G. Wittmeyer 

November 1996 

ML032720526 and ML032720528 

CNWRA 1996-001 

Study of Flow in a Fracture Under Shear: Progress Report 

Mohanty, S., R.T. Green, and K.A. Meyers-James 

October 1995 

ML040330888 

1995 

CNWRA 1995-023 

Report on the Peer Review of the Sorption Modeling for High-Level Performance Assessment 

Research Project 

Pabalan, R.T. 

September 1995 

ML040220328 

CNWRA 1995-022 

Rock Joint Model Development for Cyclic Loads 

Ghosh, A., S. Hsiung, D.J. Fox, A.H. Chowdhury, and D.D. Kana 

September 1995 
A–11 

CNWRA 1995-021 

Expert-Panel Review of Center for Nuclear Waste Regulatory Analyses (CNWRA) Coupled 

Thermal-Mechanical-Hydrological Processes Research Project 

Ahola, M.P. 

September 1995 

ML040220346 

CNWRA 1995-020 

Expert-Panel Review of the Integrated Waste Package Experiments Research Project 

Cragnolino, G.A. and N. Sridhar 

September 1995 

ML040220371 

CNWRA 1995-019 

Conceptual and Mathematical Models of the Death Valley Regional Groundwater Flow System 

Wittmeyer, G.W. and D.R. Turner 

September 1995 

ML040220379 

CNWRA 1995-018 

Initial Analysis of Selected Site-Specific Dose Assessment Parameters and Exposure Pathways 

Applicable to a Groundwater Release Scenario at Yucca Mountain 

LaPlante, P.A., S.J. Maheras, and M.S. Jarzemba 

October 1995 

ML040330891 

CNWRA 1995-017 

Faulting in the Yucca Mountain Region Critical Review and Analyses of Tectonic Data from the 

Central Basin and Range 

Ferrill, D.A., G.L. Stirewalt, D.B. Henderson, J.A. Stamatakos, A.P. Morris, K.H. Spivey, and B.P. 

Wernicke 

March 1996 

ML040330873 

CNWRA 1995-016 

Evaluation of ABAQUS as a Compliance Determination Computer Code 

Ofoegbu, G.I., A. Ghosh, M.P. Ahola, S.-M. Hsiung, and A.H. Chowdhury 

August 1995 

ML040330880 

CNWRA 1995-015 

Potential Implications of Colloids on the Long-Term Performance of a High-Level Radioactive 

Waste Repository 

Manaktala, H., D. Turner, T. Ahn, V.C. Bradley, and E. Bonano 

September 1995 

ML040160817 

CNWRA 1995-014 

Review of Empirical Thermodynamic Data for Uranyl Silicate Minerals and Experimental Plan 

Murphy, W.M. and R.T. Pabalan 

June 1995 

ML040210708 

 
A–12 

CNWRA 1995-013 

Seismic Response of Rock Joints and Jointed Rock Mass

Ghosh, A., S.-M. Hsiung, and A.H. Chowdhury 

September 1995 

ML040210700 

CNWRA 1995-012 

An Experimental Scale-Model Study of Seismic Response of an Underground Opening in Jointed 

Rock Mass 

Kana, D.D., D.J. Fox. S. Hsiung, and A.H. Chowdhury 

February 1997 

ML040210691 

CNWRA 1995-011 

Compliance Determination Computer Codes for Preclosure Safety Assessments 

Karimi, H., M. Jarzemba, H. Manaktala, A.H. Chowdhury, and M. Ahola 

June 1995 

ML040210657 

CNWRA 1995-010 

Experimental Investigations of Failure Processes of High-Level Radioactive Waste Container 

Materials 

Sridhar, N., G.A. Cragnolino, and D.S. Dunn 

May 1995 

ML040220295 

CNWRA 1995-009 

The CNWRA Regional Hydrogeology Geographic Information System Database 

Wittmeyer, G., R. Klar, G. Rice, and W. Murphy 

April 1995 

ML040220222 

CNWRA 1995-008 

Finite Element Modeling of Listric Normal Faulting 

Ofoegbu, G.I. and D.A. Ferrill 

April 1995 

ML040220216 

CNWRA 1995-007 

Iterative Performance Assessment Phase 3: Status of Activities 

Ahola, M.P., R.G. Baca, A.C. Bagtzoglou, E.J. Bonano, B. Gureghian, R.B. Hofmann, S. Hsiung, 

R.W. Janetzke, M.S. Jarzemba, H. Karimi, P.A. LaPlante, P.C. Lichtner, R.D. Manteufel, W.M. Murphy, 

D.A. Pickett, G.L. Stirewalt, and S.A. Stothoff 

April 1995 

ML040210630 

CNWRA 1995-006 

Draft Staff Technical Position of the Elicitation of Expert Judgment 

DeWispelare, A.R. and E.J. Bonano 

March 1995 

CNWRA 1995-005 

Thermally Driven Moisture Redistribution in Partially Saturated Porous Media 

Green, R.T., F.T. Dodge, S.J. Svedeman, R.D. Manteufel, G. Rice, K.A. Meyer, and R.G. Baca 

December 1995 

ML040160742 
A–13 

CNWRA 1995-004 

Progress Toward a Fractal Representation of Rock Joint Roughness 

Hsiung, S.-M., A. Ghosh, and A.H. Chowdhury 

January 1995 

ML040210608 

CNWRA 1995-003 

A Critical Review of Data in the Center for Nuclear Waste Regulatory Analyses (CNWRA) 

Volcanism Geographic Information System (GIS) Database 

Stirewalt, G.L., B.E. Hill, C.B. Connor, and C. Lin 

January 1995 

ML040160675 

CNWRA 1995-002 (Revised) 

Expert-Panel Review of CNWRA Volcanism Research Programs 

Hill, B.E. 

January 1995 

ML040220371 

CNWRA 1995-001 

A Uniform Approach to Surface Complexation Modeling of Radionuclide Sorption 

Turner, D.R. 

January 1995 

ML040160669 

CNWRA 1995-01S 

NRC High-Level Radioactive Waste Research at CNWRA January–June 1995 

Baca, R.G., A.C. Bagtzoglou, D. Balin, F.P. Bertetti, C.B. Connor, F.M. Conway, D.A. Ferrill, C.J. Goulet, 

B.E Hill, M.S. Jarzemba, R.V. Klar, P. LaFemina, P.C. Lichtner, A.P. Morris, W.M. Murphy, R.T. Pabalan, 

E.C. Pearcy, D.A. Pickett, J.D. Prikryl, K.H. Spivey, J.A. Stamatakos, S.A. Stothoff, D.R. Turner, and 

G.W. Wittmeyer 

August 1995 

ML040220368 

CNWRA 95-02S 

NRC High-Level Radioactive Waste Research at CNWRA July-December 1995 

Ahola, M.P., P. Angell, R.G. Baca, A.C. Bagtzoglou, C.B. Connor, F.M. Conway, G.A. Cragnolino, 

D.S. Dunn, D.A. Ferrill, A. Ghosh, B.E. Hill, S.M. Hsiung, M.S. Jarzemba, P.C. Lichtner, R.D. Manteufel, 

S. Mohanty, W.M. Murphy, R.T. Pabalan, E.C. Pearcy, D.A. Pickett, J.D. Prikryl, N. Sridhar, 

J.A. Stamatakos, S.A. Stothoff, D.R. Turner, and G.W. Wittmeyer. February 1996 

ML040230584 

1994 

CNWRA 1994-028 

Environmental Effects on Stress Corrosion Cracking of Type 316L Stainless Steel and Alloy 825 

as High-Level Nuclear Waste Container Materials 

Cragnolino, G.A., D.S. Dunn, and N. Sridhar 

November 1994 

ML040360661 

 
A–14 

CNWRA 1994-027 

Hydraulic Characterization of Hydrothermally-Altered Nopal Tuff 

Green, R.T., K. Meyer, and G. Rice 

December 1994 

ML040220209 

CNWRA 1994-026 

EBSPAC (Engineered Barrier System Performance Assessment Codes) Progress Report: October 

1, 1993 through September 25, 1994 

Lichtner, P.C. 

October 1994 

ML040160629 

CNWRA 1994-025 

Influence of Faults on Ascent of Mafic Magma by Dike Intrusion 

Young, S.R., H.L. McKague, and R.W. Terhune 

October 1994 

ML040160563 

CNWRA 1994-024 

Single Fracture Flow Behavior of Apache Leap Tuff Under Normal and Shear Loads 

Mohanty, S., A.H. Chowdhury, S.-M. Hsiung, and M.P. Ahola 

October 1994 

ML040360547 

CNWRA 1994-023 (Revision 1) 

A Three-Dimensional Geological Framework Model for Yucca Mountain, Nevada, With Hydrologic 

Application: Report to Accompany 1995 Model Transfer to the Nuclear Regulatory Commission 

Stirewalt, G.L. and D.B. Henderson 

September 1995 

ML040220357 

CNWRA 1994-022 

Near-Field Liquid-Vapor Transport in a Partially Saturated High-Level Nuclear Waste Repository 

Lichtner, P.C. and J.C. Walton 

October 1994 

ML040160575 

CNWRA 1994-021 

Thermo-Hydro-Mechanical Coupled Modeling: Big-Ben Experiment, 

TC3–Decovalex-Phase III 

Ahola, M.P., G.I. Ofoegbu, A.H. Chowdhury, and S.-M. Hsiung 

October 1994 

ML040230574 

CNWRA 1994-020 

BREATH Version 1.1—Coupled Flow and Energy Transport in Porous Media, Simulator 

Description and User Guide 

Stothoff, S.A. 

May 1995 

ML040780274 

 
A–15 

CNWRA 1994-019 

Background Report on the Use and Elicitation of Expert Judgment 

DeWispelare, A., L.T. Herren, E.J. Bonano, and R.T. Clemen 

September 1994 

ML040230556 

CNWRA 1994-018 

Multi-Phase Reactive Transport Theory 

Lichtner, P.C.

July 1995 

ML040160645 

CNWRA 1994-017 

Field Site Investigation: Effect of Mine Seismicity on Groundwater Hydrology 

Ofoegbu, I.G., S.M. Hsiung, A.H. Chowdhury, and J. Philip

July 1994 

ML040230536 

CNWRA 1994-016 

Invent: A Module for the Calculation of Radionuclide Inventories, Software Description, and User 

Guide 

Lozano, A.S., H. Karimi, J.P. Cornelius, R.D. Manteufel, and R.W. Janetzke 

July 1994 

ML033650226 

CNWRA 1994-015 

Strategy for the Evaluation and Use of Probability Models for Volcanic Disruptive Scenarios 

Connor, C. and B.E. Hill 

June 1994 

ML040160535 

CNWRA 1994-014 

SEISM 1.1 Test Analysis 

Hofmann, R.B 

August 1994 

ML033650242 

CNWRA 1994-013 

Geophysics Review Topical Report: Application of Seismic Tomographic and Magnetic Methods 

to Issues in Basaltic Volcanism 

Connor, C.B. and C.O. Sanders 

June 1994 

ML040160528 

CNWRA 1994-012 

Stochastic Analysis of Large-Scale Unsaturated Flow and Transport In Layered, Heterogeneous 

Media 

Bagtzoglou, A.C. and M. Muller 

June 1994 

ML040160540 

CNWRA 1994-011 

Fracture Transport of Uranium at the Nopal I Natural Analog Site 

Pearcy, E.C. 

May 1994 

ML033630674 
A–16 

CNWRA 1994-010 

Review of Degradation Modes of Alternate Container Designs and Materials 

Sridhar N., G.A. Cragnolino, D.S. Dunn, and H.K. Manaktala 

April 1994 

ML033630647 

CNWRA 1994-009 

Water Film Flow in a Fracture in Unsaturated Porous Medium 

Kapoor, V. 

May 1994 

ML033630684 

CNWRA 1994-008 

SEISMO Version 1.0: A Module for Simulation of Seismo-Mechanical Scenarios, Model 

Description, and User Guide 

Freitas, C.J., R.B. Codell, and N.A. Eisenberg 

June 1994 

ML033650215 

CNWRA 1994-007 

Effective Hydraulic Property Calculations for Unsaturated, Fractured Rock with Semi-Analytical 

and Direct Numerical Techniques: Review and Applications 

Bagtzoglou, A.C., S. Mohanty, A. Nedungadi, T.-C. Jim Yeh, and R. Ababou 

November 1994 

ML033630442 

CNWRA 1994-006 

Geochemical Investigations Related to the Yucca Mountain Environment and Potential Nuclear 

Waste Repository 

Murphy, W. and R. Pabalan 

March 1994 

ML033630657 

CNWRA 1994-005 

DRILLO CODE: A Module for Simulation of Human Intrusion Scenarios, Model Description, and 

User Guide—IPA Phase 2 

Freitas, C.J., N.A. Eisenberg, and R.G. Baca 

February 1994 

 ML033630426 

CNWRA 1994-004 

The Center for Nuclear Waste Regulatory Analyses (CNWRA) Volcanism Geographic Information 

System Database 

Connor, C.B. and B.E. Hill 

January 1994 

CNWRA 1994-003 

Substantially Complete Containment—Example Analysis of a Reference Container 

Cragnolino, G., N. Sridhar, J. Walton, R. Janetzke, T. Torng, J.Wu, and P. Nair 

January 1994 

ML033640232 

 
A–17 

CNWRA 1994-002 

Review of Scenario Selection Approaches for Performance Assessment of High-Level Waste 

Repositories and Related Issues 

Bonano, E.J. and R.G. Baca 

February 1994 

ML033640272 

CNWRA 1994-001 

Evaluation of Computer Codes for Compliance Determination Phase II 

Ghosh, A., S.M. Hsiung, G.I. Ofoegbu, and A.H. Chowdhury 

January 1994 

CNWRA 1994-02S 

NRC High-Level Radioactive Waste Research at CNWRA: July–December 1994 

Ahola, M.P., R.G. Baca, F.P. Bertetti, A.H. Chowdhury, C.B. Connor, G.A. Cragnolino, D.S. Dunn, 

D.A. Ferrill, D.B. Henderson, B.E. Hill, S.M. Hsiung, D.D. Kana, R.V., Klar, P.C. Lichtner, R.H. Martin, 

S. Mohanty, A.P. Morris, W.M. Murphy, R.T. Pabalan, E.C. Pearcy, J.D. Prikryl, N. Sridhar, S.A. Stothoff, 

D.R. Turner, and G.W. Wittmeyer 

February 1995 

ML040210615 

CNWRA 1994-01S 

NRC High-Level Radioactive Waste Research at CNWRA for January through June 1994 

Ahola, M.P., R.G. Baca, F.P. Bertetti, A.H. Chowdhury, C.B. Connor, G.A. Cragnolino, D.S. Dunn, 

R.T. Green, D.A. Ferrill, D.B. Henderson, B.E. Hill, S.M. Hsiung, R.C. Lichtner, S. Mohanty, A.P. Morris, 

W.M. Murphy, G.l. Ofoegbu, R.T. Pabalan, E.C. Pearcy, N. Sridhar, G.L. Stirewalt, S.A. Stothoff, 

D.R. Turner, G.W. Wittmeyer, and S.R. Young. 

September 1994. 

ML040230547 

1993 

CNWRA 1993-024 

Evaluation of Rock Joint Models and Computer Code UDEC Against Experimental Results 

Hsiung, S.M., A. Ghosh, A.H. Chowdhury, and M.P. Ahola 

December 1993 

ML033640188

CNWRA 93-023 

(unidentified) 

CNWRA 93-022 

(unidentified) 

CNWRA 1993-021 

Engineered Barrier System Performance Assessment Codes (EBSPAC) Progress 

Report—October 1, 1992 Through September 25, 1993 

Sridhar, N., J.C. Walton, G.A. Cragnolino, and P.K. Nair 

October 1993 

ML040200634 

 
A–18 

CNWRA 1993-020 

The Role of Natural Analog in Geologic Disposal of High-Level Nuclear Waste 

Apps, J.A., J.W. Bradbury, R.E. Cady, R.C. Ewing, D.L. Gustafson, R.B. Hofmann, D.T. Hoxie, 

L.A. Kovach, M.B. McNeil, W.M. Murphy, W.R. Ott, E.C. Pearcy, B. Sagar, M.E. Shea, N. Sridhar, 

G.W. Wittmeyer, J.R. Wood, and S.R. Young 

September 1993 

ML040360540 

CNWRA 1993-019 

Mechanistic Approaches to Radionuclide Sorption Modeling 

Turner, D.R. 

September 1993 

ML040200620 

CNWRA 1993-018 

A Review and Analysis of Dating Techniques for Neogene and Quaternary Volcanic Rocks 

Hill, B.E., B.W. Leslie, and C.B. Connor 

September 1993 

ML040200609 

CNWRA 1993-017 

Total-System Performance Assessment (TPA) Computer Code: Description of Executive Module, 

Version 2.0 

Sagar, B. and R. Janetzke 

August 1993 

ML033630420 

CNWRA 1993-016 

Expert Elicitation of Future Climate in the Yucca Mountain Vicinity 

DeWispelare, A.R., L.T. Herren, R.T., Clemen, and M.P. Miklas 

August 1993 

ML033630407 

CNWRA 1993-015 

CNWRA 1993-014 

A Review of the Potential for Microbially Influenced Corrosion of High-Level Waste Containers 

Geesey, G. 

June 1993 

ML040230184 

CNWRA 1993-013 

Laboratory Characterization of Rock Joints 

Hsiung, S.M., D.D. Kana, M.P. Ahola, A.H. Chowdhury, and A. Ghosh 

September 1993 

ML040200657 

CNWRA 1993-012 

Uranium Mineralogy of the Nopal I Natural Analog Site, Chihuahua, Mexico

Pearcy, E.C., J.D. Prikryl, W.M. Murphy, and B.W. Leslie 

June 1993 

ML033650119 

 
A–19 

CNWRA 1993-011 

Development Plan PASS/PADB System Design Version 3.0 

DeWispelare, A.R., R.D. Johnson, R.L. Marshall, and J.H. Cooper 

May 1993 

CNWRA 1993-010 

Volcano Code—A Module for Simulation of Magmatic Scenario Model Description and User Guide: 

Iterative Performance Assessment Phase 2 

Lin, C.S., R.G. Baca, and R. Drake 

October 1993 

ML040690228 

CNWRA 1993-009 

Open Item Tracking System (OITS) Version 1.0 User's Guide 

McFaddin, S.K., R.L. Marshall, R.D. Carlson, and R.L. Johnson 

July 1993 

ML033650183 

CNWRA 1993-008 

Review of Corrosion Aspects of High-Level Waste Storage Tanks at West Valley 

Cragnolino, G.A. 

April 1993 

ML033630389 

CNWRA 1993-007 

Seismic/Tornado Analysis Review for the Vitrification Facility at West Valley

Pomerening, D.J., C. Tschoepe, and P.K. Nair 

April 1993 

ML040200332 

CNWRA 1993-006 

Characteristics of Spent Nuclear Fuel and Cladding Relevant to High-Level Waste Source Term 

Manaktala, H.K. 

March 1993 

ML040200340 

CNWRA 1993-005 

Evaluation of Coupled Computer Codes for Compliance Determination 

Ghosh, A., S.-M. Hsiung, M.P. Ahola, and A.H. Chowdhury 

June 1993 

ML033650129 

CNWRA 1993-004 

Experimental Investigations of Localized Corrosion of High-Level Waste Container Materials 

Sridhar, N., G.A. Cragnolino, and D. Dunn 

February 1993 

ML040200255 

CNWRA 1993-003 

Long-Term Stability of High-Level Waste Container Materials: I-Thermal Stability of Alloy 825 

Cragnolino, G. and N. Sridhar 

February 1993 

ML040200291 
A–20 

CNWRA 1993-002 

Thermo-Hydro-Mechanical Coupled Modeling: Near-Field Repository Model, BMT3 

Chowdhury, A.H. 

August 1993 

ML040200648 

CNWRA 1993-001 

Repository Isolation Criteria Study Recommendation Report 

DeWispelare, A. and P. LaPlante 

January 1993 

ML040200243 

CNWRA 1993-02S 

NRC High-Level Radioactive Waste Research at CNWRA for July through December 1993 

Ahola, M., R. Baca, A. Chowdhury, C. Connor, G. Cragnolino, F. Dodge, D. Dunn, A. Ghosh, R. Green, 

B. Hill, S. Hsiung, V. Kapoor, R. Manteufel, S. McDuffie, S. Mohanty, W. Murphy, R. Pabalan, E. Pearcy, 

N. Sridhar, G. Stirewalt, S. Stothoff, D. Turner, G. Wittmeyer, and S. Young 

February 1994 

ML033650211 

CNWRA 1993-01S 

NRC High-Level Radioactive Waste Research at CNWRA for January through June 1993 

Ahola, M., R. Baca, A. Bagtzoglou, A.H. Chowdhury, C.B. Connor, G. Cragnolino, D. Dunn, A. Ghosh, 

R. Green, B. Henderson, B. Hill, S. Hsiung, B. Leslie, R. Manteufel, R. Martin, S. Mohanty, W. Murphy, 

R. Pabalan, E. Pearcy, N. Sridhar, D.R. Turner, G.W. Wittmeyer, and S.R. Young 

August 1993 

ML033650178 

1992 

CNWRA 1992-027 

Review and Analysis of the PASS/PADB System for Systematic Regulatory Analysis 

DeWispelare, A., J. Cooper, R. Johnson, and R. Marshall 

December 1992 

ML040200216 

CNWRA 1992-026 

BIGFLOW: A Multi Dimensional Code Flow in Heterogeneous and Variably Saturated Geologic 

Media (Theory and User's Manual - Version 1.0) 

Ababou, R. and R. Bagtzoglou 

December 1992 

ML040690221 

CNWRA 1992-025 

A Review of Pertinent Literature on Volcanic-Magmatic and Tectonic History of the Basin and 

Range 

Stirewalt, G., S.R. Young, and K.D. Mahrer 

September 1992 

ML033650055 

CNWRA 1992-024 

Preliminary Structural Interpretation of Reflection Seismic Line AV-1 

Young, S.R., A.P. Morris, and G.L. Stirewalt 

November 1992 

ML040200192 
A–21 

CNWRA 1992-023 

(unidentified) 

CNWRA 1992-022 

Natural Resources Regulatory Requirements: Background and Consideration of Compliance 

Methodologies 

Miklas, M.P., J.L. Russell, D.R. Turner, E.C. Pearcy, and S. Spector 

September 1992 

ML033650034 

CNWRA 1992-021 

A Review of Stress Corrosion Cracking of High-Level Nuclear Waste Containers Materials 

Cragnolino, G. and N. Sridhar 

August 1992 

ML033640122 

CNWRA 1992-020 

MARIANA—A Simple Chemical Equilibrium Module , Version 1.0 

Walton, J.C. and S.K. Kalandros 

August 1992 

ML033640065 

CNWRA 1992-019 

TWITCH—A Model for Transient Diffusion, Electromigration, and Chemical Reaction in One 

Dimension, Version 1.0 

Walton, J.C., and S.K. Kalandros 

August 1992 

ML033640116 

CNWRA 1992-018 

Leaching of Borosilicate Glass Using Draft ASTM Procedure for High-Level Waste 

Manaktala, H. 

August 1992 

ML033420053 

CNWRA 1992-017 

An Assessment of Borosilicate Glass as a High-Level Waste Form 

Manaktala, H.K. 

September 1992 

ML033650021 

CNWRA 1992-016 

Substantially Complete Containment (SCC) Elicitation Report 

Tschoepe, E. and L.R. Abramson 

August 1992 

ML033640128 

CNWRA 1992-015 

(unidentified) 

CNWRA 1992-014 

Site Selection and Workplan Report for the Geochemical Natural Analog Research Project 

Pearcy, E.C. and W.M. Murphy 

July 1992 
A–22 

CNWRA 1992-013 

(unidentified) 

CNWRA 1992-012 

Field Site Investigation: Effect of Mine Seismicity on a Jointed Rock Mass 

Chowdhury, A., S. Hsiung, W. Blake, M. Ahola, and A. Ghosh

December 1992 

ML040200235 

CNWRA 1992-011 

A Literature Review of Coupled Thermal-Hydrologic-Mechanical-Chemical Processes Pertinent to 

the Proposed High-Level Nuclear Waste Repository 

Manteufel, R.D., M.P. Ahola, D.R. Turner, and A.H. Chowdhury 

August 1992 

ML012750463 

CNWRA 1992-010 

Functional Needs Update and Status Report on the DHLWM Advanced Computer Review System 

Johnson, R.D., R.L. Marshall, and S.W. Dellenback 

May 1992 

ML040630424 

CNWRA 1992-009 

A Source Term Code for High-Level Nuclear Waste Geologic Repositories 

Sagar, B., R.B. Codell, J. Walton, and R.W. Janetzke 

July 1992 

ML033640032 

CNWRA 1992-008 

Geometric Models of Faulting at Yucca Mountain 

Young, S.R., G.L. Stirewalt, and A.P. Morris 

October 1992 

ML033650098 

CNWRA 1992-007 

Repository Operational Criteria Comparative Analysis 

Hageman, J.P. and A.H. Chowdhury 

June 1994 

CNWRA 1992-006 

Theoretical and Experimental Investigation of Thermohydrologic Processes in a Partially 

Saturated, Fractured Porous Medium 

Green, R. T., R.D. Manteufel, F.T. Dodge, and S.J. Svedeman 

July 1993 

ML040330762 

CNWRA 1992-005 

Thermo-Hydro-Mechanical Coupled Modeling: Multiple Fracture Model, BMT2; Coupled 

Stress-Flow Model, TC1, DECOVALEX Phase 1 

Ahola, M.P. S.-M. Hsiung, L.J. Lorig, and A.H. Chowdhury 

April 1992 

 ML040330769 

 
A–23 

CNWRA 1992-004 

Effects of Layering, Dipping Angle, and Faulting on Two-Dimensional Variably Saturated Flow, 

Iterative Performance Assessment—Phase II 

Bagtzoglou, A.C., R. Ababou, and B. Sagar 

February 1992 

 ML033640017 

CNWRA 1992-003 

PORFLOW: A Multifluid Multiphase Model for Simulating Flow, Heat Transfer, and Mass Transport 

in Fractured Porous Media 

Runchal, A.K. and B. Sagar 

February 1992 

ML040220612 

CNWRA 1992-002 

Sensitivity and Uncertainty Analyses Applied to One-Dimensional Transport in a Layered, 

Fractured Rock. Part 2: Evaluation of Limit State Approach, Iterative Performance Assessment, 

Phase II 

Wu, Y.-T., A.B. Gureghian, B. Sagar, and R.B. Codell 

March 1992 

ML040330673 

CNWRA 1992-001 

Regional Groundwater Modeling of the Saturated Zone in the Vicinity of Yucca Mountain, Nevada 

Ahola, M., and B. Sagar 

January 1992 

ML040630369 

CNWRA 1992-02S 

NUREG/CR-5817: Volume 3, No. 2: NRC High-Level Radioactive Waste Research at CNWRA 

Ababou, R., M. Ahola, R.G. Baca, A.C. Bagtzoglou, A.H. Chowdhury, C.B. Connor, G. Cragnolino, 

F.T. Dodge, A. Ghosh, R.T. Green, B.H. Hill, S.M. Hsiung, B.W. Leslie, R.D. Manteufel, W.M. Murphy, 

R.T. Pabalan, E.C. Pearcy, N. Sridhar, G. Stirewalt, D.R. Turner, G.W. Wittmeyer, and S. Young 

July 1993 

CNWRA 1992-01S 

NUREG/CR-5817: Volume 3, No. 1: NRC High-Level Radioactive Waste Research at CNWRA 

R. Ababou, M. Ahola, R.G. Baca, A.H. Chowdhury, G. Cragnolino, R.T. Green, S.M. Hsiung, B.W. Leslie, 

R.D. Manteufel, W.M. Murphy, R.T. Pabalan, E.C. Pearcy, J.D. Prikryl, B. Sagar, N. Sridhar, G. Stirewalt, 

D. Turner, G. Wittmeyer, and S. Young 

January 1992 

1991 

CNWRA 1991-016 

Effects of Variable Hydrologic Saturation on Sorption Modeling for High-Level Waste Performance 

Assessment a Literature Review 

Turner, D.R. 

December 1991 

ML003755802 

 
A–24 

CNWRA 1991-015 

Safety Evaluation Report on the West Valley Demonstration Project Supernatant Treatment 

System {A Review of Safety Analysis Report, Volume III, Part D (WVNS SAR-004, Revision 6)}

Tschoepe, E., H. Karimi, G. Lamping, and P. Nair 

November 1991 

ML040780163 

CNWRA 1991-014 

Repository Operational Criteria Analysis 

Hageman, J.P. and A.C. Chowdhury 

June 1992 

CNWRA 1991-013 

Probabilistic Fault Displacement and Seismic Hazard Analysis Literature Review 

Hofmann, R.B. 

November 1991 

ML040780259 

CNWRA 1991-012 

Draft Options Paper on Groundwater Travel Time as the Performance Measure of the Geologic 

Setting of a High-Level Radioactive Waste Geologic Repository 

Green, R.T., M.P Miklas, and G.W. Wittmeyer 

August 1991 

CNWRA 1991-011 

Sorption Modeling for High-Level Waste Performance Assessment: A Literature Review 

Turner, D.R. 

August 1992 

ML040220147 

CNWRA 1991-010 

Sensitivity and Uncertainty Analyses Applied to One-Dimensional Radionuclide Transport in a 

Layered Fractured Rock 

Gureghian, A.B., Y.T. Wu, B. Sagar, and R.B. Codell 

August 1991 

 ML040220140 

CNWRA 1991-009 

Total System Assessment Computer Code: Description of Executive Module 

Sagar, B. and R.W. Janetzke 

July 1991 

ML040230527 

CNWRA 1991-008 

Hydrogen Absorption and Embrittlement of Candidate Container Materials 

Sridhar, N., B.E. Wilde, C. Manfredi, S. Kesavan, and C. Miller 

June 1991 

ML040330594 

CNWRA 1991-007 

Proceedings of Workshop V: Flow and Transport Through Unsaturated Fractured Rock-Related to 

High-Level Radioactive Waste Disposal, Radisson Suite Hotel, Tucson, Arizona, January 7–10, 

1991 

Evans, D.D. and T.J. Nicholson 

January 1991 

ML012750478 
A–25 

CNWRA 1991-006 

Draft Acceptable Methodology for Assessment of the Natural Resources of a Proposed High-Level 

Waste Repository Site 

Pearcy, E. and M. Miklas 

June 1991 

CNWRA 1991-005 

RDFREE: A Fortran Utility for Format Free Input—User's Guide 

Janetzke, R.W. and B. Sagar 

June 1991 

ML040210568 

CNWRA 1991-004 

A Review of Localized Corrosion of High-Level Nuclear Waste Container Materials 

Cragnolino, G. and N. Sridhar 

April 1991 

ML040330605 

CNWRA 1991-003 

preFOR: A Pre-Processor for Fortran Files User's Manual 

Janetzke, R.W. and B. Sagar 

April 1991 

ML040210564 

CNWRA 1991-002 

Approaches to Large Scale Unsaturated Flow in Heterogeneous, Stratified , and Fractured 

Geologic Media 

Ababou, R. 

April 1991 

CNWRA 1991-001 

High-Level Radioactive Waste Repository Functional Analysis 

Romine, D.T. 

March 1992 

ML003751111 

CNWRA 1991-03Q 

Report on Research Activities for the Quarter July 1, 1991 through September 30, 1991 

Patrick, W.C. (ed.) 

November 1991 

ML040360622 

CNWRA 1991-02Q 

Research Activities for the Quarter April 1 through June 30, 1991 

Patrick, W.C. (ed.) 

August 1991 

ML040360615 

CNWRA 1991-01Q 

Report on Research Activities for the Quarter January 1 through March 31, 1991 

Patrick, W.C. (ed.) 

May 1991 

 ML040360628 

 
A–26 

CNWRA 1991-01A 

Report on Research Activities for Calendar Year 1991 

Patrick, W.C. (ed.) 

February 1992 

ML040780247 

1990 

CNWRA 1990-008 

Geochemical Natural Analogs Literature Review 

Pearcy, E.C. and W.M. Murphy 

June 1991 

ML040330616 

CNWRA 1990-007 

Substantially Complete Containment Feasibility Assessment and Alternatives Report 

Nair, P.K. and E.C. Tschoepe 

September 1990 

ML040130656 

CNWRA 1990-006 

Qualification Studies on the Finite Element Code Hondo II Against Some Benchmark Analytical 

Problems 

Brandshaug, T., B. Dasgupta, B.H.G. Brady, S.-M. Hsiung, and A.H. Chowdhury 

February 1990 

ML040690163 

CNWRA 1990-005 

Development of a Rock Joint Dynamic Shear Test Apparatus 

Kana, D.D., D.C. Scheidt, B.H.G. Brady, A.H. Chowdhury, S.-M. Hsiung, and B.W. Vanzant 

January 1990 

ML040780170 

CNWRA 1990-004 

Qualification Studies on the Distinct Element Code UDEC Against Some Benchmark Analytical 

Problems 

Brady, B.H., S.M. Hsiung, and A.H. Chowdhury 

January 1990 

ML040690187 

CNWRA 1990-003 

Identification and Evaluation of Regulatory and Institutional Uncertainties in 10 CFR Part 60, 

Volume 2—Identification 

Weiner, R.F., W.C. Patrick, and D.T. Romine 

February 1990 

ML040780158 

CNWRA 1990-003 

Identification and Evaluation of Regulatory and Institutional Uncertainties in 10 CFR Part 60, 

Volume 1—Evaluation 

Weiner, R.F., W.C. Patrick, and D.T. Romine 

February 1990 

ML040780253 

 
A–27 

CNWRA 1990-002 

Draft: Uncertainty Evaluation Methods for Waste Package Performance Assessment 

Wu, Y.T., A.G. Journel, L.R. Abramson, and P.K. Nair 

March 1990 

CNWRA 1990-001 

Technical Considerations and an Approach for Evaluating "Substantially Complete Containment" 

of High-Level Nuclear Waste 

Manaktala, H.K. and C.G. Interrante 

March 1990 

CNWRA 1990-03Q 

Report on Research Activities for the Quarter July 1 through September 30, 1990 

Patrick, W.C. (ed.) 

November 1990 

ML040360607 

CNWRA 1990-02Q 

Report on Research Activities for the Quarter April 1 through June 30, 1990 

Patrick, W.C. (ed.) 

August 1990 

ML040780271 

CNWRA 1990-01Q 

Report on Research Activities for the Quarter January 1 through March 31,1990 

Patrick, W.C. (ed.) 

May 1990 

ML040260078 

CNWRA 1990-01A 

Report on Research Activities for Calendar Year 1990 

Ababou, R., A.H. Chowdhury, G. Cragnolino, F.T. Dodge, R.T. Green, A.B. Gureghian, S.M. Hsiung, 

W.M. Murphy, R.T. Pabalan, E.C. Pearcy, B. Sagar, and N. Sridhar 

February 1991 

ML040780247 

1989 

CNWRA 1989-006 

Progress in Experimental Studies on the Thermodynamic and Ion Exchange Properties 

of Clinoptilolite 

Pabalan, R.T. and W.M. Murphy 

January 1990 

ML040690193 

CNWRA 1989-005 

(unidentified) 

CNWRA 1989-004 

Strategic Programmatic Issues and Risks Related to Comprehensive Planning for the High-Level 

Waste Program 

Greenberg, R.E. and R.B. Adler 

June 1989 

ML040690172 
A–28 

CNWRA 1989-003 

Analysis and Evaluation of Regulatory Uncertainties in 10CFR60 Subparts B and E 

Patrick, W.C. and R.F. Weiner 

May 1989 

ML040780239 

CNWRA 1989-002 

Analysis and Evaluation of Regulatory Uncertainties Related to the Site Characterization Plan and 

the Exploratory Shaft Facility 

Weiner, R. F. and W.C. Patrick 

April 1989 

ML040780243 

CNWRA 1989-001 

NUREG/CR-5440: Critical Assessment of Seismic and Geomechanics Literature Related to a 

High-Level Nuclear Waste Underground Repository 

Kana, D.D, B.H.G. Brady, B.W. Vanzant, and P. K. Nair 

June 1991 

1988 

CNWRA 88-004 

Fast Probabilistic Performance Assessment (FPPA) Methodology Evaluation 

Wu, Y. and P. Nair 

October 1988 

ML022770058 

CNWRA 88-003 

Environmental Statement on the Transportation of Radioactive Material in the United States 

Oelkers, E.A.,R.N. Pierce, R.L. Mason, and J. Buckingham 

September 1988 

CNWRA 88-002 

Convo Evaluation and Enhancement Plan 

Wu, Y., P. Nair, G. Fuller, and R. Moler 

September 1988 

CNWRA 88-001 

Review of the Literature Relevant to the Transportation Risk Study 

Oelkers, E., and R.N. Pierce 

March 1988