alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
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# Guidance on Developing Effective Radiological Risk Communication Messages: Effective Message Mapping and Risk Communication with the Public in Nuclear Plant Emergency Planning Zones (NUREG/CR-7033)

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## Publication Information

**Manuscript Completed:** June 2010**Date Published:** February 2011

**Prepared by:** V.T. Covello

Center for Risk Communication 415 East 5 2 nd Street, Suite 3DA New York, NY 10022

P.A. Milligan, NRC Technical Lead A.M. Stang, NRC Project Manager

NRC Job Code R3138

Office of Nuclear Security and Incident Response U.S. Nuclear Regulatory Commission Washington DC 20555-0001

Availability Notice

## Abstract

This document provides guidance for nuclear power plant licensees and local response organizations on message development for radiological emergencies. Message development skills are critical to successful radiological risk communication to the public, the media, and other stakeholders. Message development skills are particularly critical to successful emergency communications with those living in close proximity to a nuclear power plant.

This document contains principles, strategies, and tools for producing messages before, during, and after a radiological emergency that are understandable, timely, accurate, consistent, and credible. The document contains nearly 400 questions the public and media may ask during a radiological emergency.

The document describes one of the most important tools for message development: the message map. Message maps are used by a large number of public and private sector organizations. Message maps are risk communication tools used to help organize complex information and make it easier to express current knowledge.

Message mapping is a science-based message development process by which users can:
        - anticipate questions of stakeholders (interested, affected, or influential parties) before they are raised;
        - decide what questions they want or need to answer and what questions should be answered by other organizations;
        - develop responses to stakeholder questions in a clear, concise, and accessible format;
        -  promote dialogue about messages both inside and outside the organization;
        - provide spokespersons with a user-friendly guide to a set of vetted organizational messages;
        - ensure the organization has consistent messages;
        - ensure the organization speaks with a single voice or with many voices in harmony.

Page Last Reviewed/Updated Wednesday, March 24, 2021
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# Post-Test Calculation of the ROSA/LSTF Test 3-2 using RELAP5/mod3.3 (NUREG/IA-0410)

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        - NUREG/IA-0410 (PDF - 1.58 MB)

## Publication Information

**Manuscript Completed:** January 2012**Date Published:** March 2012

**Prepared by:** V. Martinez, F. Reventós, C. Pretel

Institute of Energy Technologies Technical University of Catalonia ETSEIB, Av. Diagonal 647, Pav. C 08028 Barcelona, SPAIN

A. Calvo, NRC Project Manager

Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

**Published by:** U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

Availability Notice

## Abstract

The Thermalhydraulic Studies Group of Technical University of Catalonia (UPC) holds a large background in nuclear safety studies in the field of Nuclear Power Plant (NPP) code simulators. This report analyzes with RELAP5mod3.3 the LSTF Test 3-2, which simulates a loss-of-feedwater transient (LOFW) without scram and with a total failure of the high pressure injection system (HPIS). The simulation of several phenomena related with the high power natural circulation has been object of study as well as the impact of the environment heat losses in the primary coolant discharge across the pressurizer power-operated relief valve (PORV).

Page Last Reviewed/Updated Tuesday, March 09, 2021
No. 91-677.

#### Simon *v.*Simon et al.

C. A. 5th Cir. Certiorari denied.
EXHIBIT 32 CERTIFICATIONS OF PRINCIPAL EXECUTIVE OFFICER AND PRINCIPAL FINANCIAL OFFICER PURSUANT TO 18 U.S.C. SECTION 1350, AS ADOPTED PURSUANT TO SECTION 906 OF THE SARBANES-OXLEY ACT OF 2002 In connection with Amendment No. 1 to the Annual Report of Micromet, Inc. (the Company) on Form 10-K/A for the fiscal year ended December 31, 2010 as filed with the Securities and Exchange Commission on the date hereof (the Amended Report), I, Christian Itin, President and Chief Executive Officer of the Company, certify, pursuant to 18 U.S.C. Section 1350, as adopted pursuant to Section 906 of the Sarbanes-Oxley Act of 2002, that to my knowledge: 1.

          The Amended Report fully complies with the requirements of Section 13(a) or 15(d) of the Securities Exchange Act of 1934; and 2.

          The information contained in the Amended Report fairly presents, in all material respects, the financial condition of the Company at the end of the period covered by the Amended Report and results of operations of the Company for the period covered by the Amended Report.  Date: April 15, 2011

          

          /s/ Christian ItinChristian Itin President and Chief Executive Officer (principal executive officer)
 This certification accompanies the Amended Report and shall not be deemed filed by the Company with the Securities and Exchange Commission and is not to be incorporated by reference into any filing of the Company under the Securities Act of 1933, as amended, or the Securities Exchange Act of 1934, as amended (whether made before or after the date of the Amended Report), irrespective of any general incorporation language contained in such filing. 
 In connection with Amendment No. 1 to the Annual Report of Micromet, Inc. (the Company) on Form 10-K/A for the fiscal year ended December 31, 2010 as filed with the Securities and Exchange Commission on the date hereof (the Amended Report), I, Barclay A. Phillips, Senior Vice President and Chief Financial Officer of the Company, certify, pursuant to 18 U.S.C. Section 1350, as adopted pursuant to Section 906 of the Sarbanes-Oxley Act of 2002, that to my knowledge: 1.

          The Amended Report fully complies with the requirements of Section 13(a) or 15(d) of the Securities Exchange Act of 1934; and 2.

          The information contained in the Amended Report fairly presents, in all material respects, the financial condition of the Company at the end of the period covered by the Amended Report and results of operations of the Company for the period covered by the Amended Report.  Date: April 15, 2011

          

          /s/ Barclay PhillipsBarclay Phillips Senior Vice President and Chief Financial Officer (principal financial officer)
 This certification accompanies the Amended Report and shall not be deemed filed by the Company with the Securities and Exchange Commission and is not to be incorporated by reference into any filing of the Company under the Securities Act of 1933, as amended, or the Securities Exchange Act of 1934, as amended (whether made before or after the date of the Amended Report), irrespective of any general incorporation language contained in such filing.
Exhibit 32.1 CERTIFICATION OF CHIEF EXECUTIVE OFFICER PURSUANT TO 18
U.S.C. SECTION 1350,
AS ADOPTED PURSUANT TO SECTION 906
OF THE SARBANES-OXLEY ACT OF 2002 In
connection with the Quarterly Report of Speedus Corp. (the Company) on Form
10-Q for the period ending June 30, 2007 as filed with the Securities and
Exchange Commission on the date hereof
(the Report), I, Shant S. Hovnanian, Chairman of the Board, President and
Chief Executive Officer of the Company,
certify, pursuant to 18 U.S.C. Section 1350, as adopted pursuant to Section 906
of the Sarbanes-Oxley Act of 2002,
that: (1)
The Report
 fully complies with the requirements of Section 13(a) or 15(d) of the
 Securities Exchange of 1934, amended; and(2)
The
 information contained in the Report fairly presents, in all material
 respects, the financial condition and results of operations of the Company.  Date:
August 14,
 2007By:
/s/ Shant S.
 HovnanianName:
Shant S.
 HovnanianTitle:
Chairman of
 the Board, President and Chief Executive Officer 20
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# RELAP/MOD2 Calculations of OECD-LOFT Test LP-SB-03 (NUREG/IA-0013)

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        - NUREG/IA-0013 (PDF 1.49 MB)

## Publication Information

**Date Published:** January 1990

**Prepared by:** C. Harwood, G. Brown

Central Electricity Generating Board Barnwood, Gloucester GL4 7RS United Kingdom

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)

**Published by:** Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555

Availability Notice

## Abstract

This report compares the results of the RELAP5/MOD2 analysis with experimental measurements.

A simulation of test LP-SB-03 was previously carried out at GDCD using the RELAP5/MOD1 code. RELAP5/MOD2 was developed from RELAP5/MOD1 and contains more sophisticated hydraulic models and constitutive relationships. Comparison of the RELAP5/MOD2 and MODI calculations show that RELAP5/MOD2 performs better than RELAP5/MOD1 in a number of key areas; notably mass errors are much reduced, there is improved numerical stability, and improved separator modelling and modelling of accumulator injection.

Page Last Reviewed/Updated Tuesday, March 09, 2021
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# (Availability of) An International Report on Safety Critical Software for Nuclear Reactors by the Regulator Task Force on Safety Critical Software (TF-SCS) (NUREG/IA-0463)

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        - NUREG/IA-0463 (PDF - 2.14 MB)

## Publication Information

**Manuscript Completed:**August 2014**Date Published:** December 2015

**Prepared by:** Sushil Birla, Russell Sydnor

Norbert Carte, NRC Project Manager

Division of Engineering Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

**Prepared as part of:** Prepared as part of the technical exchange and cooperation between the U.S. Nuclear Regulatory Commission and the Task Force for Safety Critical Software in the Field of Nuclear Safety Research

**Published by:** U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

Availability Notice

## Abstract

The Regulator Task Force on Safety Critical Software (TF SCS) for nuclear reactors, which is comprised of seven international nuclear regulators and authorized technical-support organizations, and the U.S. Nuclear Regulatory Commission (NRC) have exchanged information seeking consistency in the technical basis for licensing reviews of software in safety-related digital instrumentation and control systems for nuclear power plants. The TF SCS has documented its consensus technical basis in the enclosed technical report and invited the NRC’s review and comments. Although the NRC is not a member of the TF SCS, the NRC staff have participated in meetings and provided comments on the TF SCS report. As a result, the NRC collaborated with the TF SCS by reviewing and providing comments to improve the technical report documenting the TF SCS’s common positions. This NUREG includes the TF SCS report titled "Licensing of Safety Critical Software for Nuclear Reactors - Common Position of International Nuclear Regulators and Authorised Technical Support Organisations." The NRC added an Appendix after the TF SCS report to assist NRC staff in using the information as a technical reference in any future changes to NRC’s regulatory guidance framework.

Page Last Reviewed/Updated Tuesday, March 09, 2021
UNPUBLISHED

UNITED STATES COURT OF APPEALS

FOR THE FOURTH CIRCUIT

No. 96-6652

UNITED STATES OF AMERICA,

Plaintiff - Appellee,

versus

GERALD VAUGHN BEASLEY,

Defendant - Appellant.

Appeal from the United States District Court for the Western District of Virginia, at Roanoke. James C. Turk, District Judge.

(CR-92-30, CA-95-465-R)

Submitted: November 7, 1996 Decided: November 19, 1996

Before RUSSELL and WIDENER, Circuit Judges, and PHILLIPS, Senior

Circuit Judge.

Affirmed by unpublished per curiam opinion.

Gerald Vaughn Beasley, Appellant Pro Se. Donald Ray Wolthuis,

OFFICE OF THE UNITED STATES ATTORNEY, Roanoke, Virginia, for

Appellee.

Unpublished opinions are not binding precedent in this circuit.

See Local Rule 36(c).
2

PER CURIAM:

Appellant appeals from the district court's order denying his

motion filed under 28 U.S.C. § 2255 (1994), amended by Antiterrorism and Effective Death Penalty Act of 1996, Pub. L. No. 104-

132, 110 Stat. 1214. We have reviewed the record and the district

court's opinion and find no reversible error. Accordingly, we

affirm on the reasoning of the district court. United States v.

Beasley, Nos. CR-92-30; CA-95-465-R (W.D. Va. Apr. 9, 1996). We

dispense with oral argument because the facts and legal contentions

are adequately presented in the materials before the court and

argument would not aid the decisional process.

AFFIRMED
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# Aluminum Chemistry in a Prototypical Post-Loss-of-Coolant-Accident, Pressurized-Water-Reactor Containment Environment (NUREG/CR-6915)

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        - NUREG/CR-6915 (PDF - 19.2 MB)

## Publication Information

**Manuscript Completed:**August 2006**Date Published:**December 2006

Principal Investigator: M. Klasky

**Prepared by:** M. Klasky, J. Zhang, M. Ding, and B. Letellier (Los Alamos National Laboratory) D. Chen and K. Howe (University of New Mexico)

Los Alamos National Laboratory Los Alamos, NM 87545

University of New Mexico Department of Civil Engineering Albuquerque, NM 87110

T.Y. Chang, NRC Project Manager

**Prepared for:**Division of Fuel, Engineering and Radiological Research Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

NRC Job Code N6285

Availability Notice

## Abstract

An analysis of the integrated chemical effects tests (ICET) experiments has been performed by a comprehensive examination of both the test solutions and precipitates. In addition, a comprehensive review of the literature has been performed to assist in explaining the behavior of aluminum in alkaline solutions. The objective of this analysis was to elucidate the behavior of precipitate that formed when the ICET Tests 1 and 5 solutions were allowed to cool so that the behavior of other solutions with different conditions, i.e., pH, temperature, etc., could be predicted throughout the pressurized water reactor following a loss-of-coolant accident (LOCA). This examination included supplemental analytical measurements using x-ray diffraction, 27Al and 11B nuclear magnetic resonance for both liquid and solid states, and quasi-elastic light-scattering measurements. Surrogate solutions were developed and compared with the analytical measurements of the ICET Tests 1 and 5 solutions. Finally, the characterization of the particle sizes and corrosion properties, including the corrosion mechanism and the corrosion rate of aluminum under LOCA conditions, has been elucidated. The current study should allow for the development of a head-loss correlation using the existing cake filtration theory, which could be used in conjunction with a corrosion model to predict system performance following a LOCA.

Page Last Reviewed/Updated Wednesday, March 24, 2021
## NUMBER 13

- 20

- 000 26

- C R

COURT OF APPEALS

THIRTEENTH DISTRICT OF TEXAS

CORPUS CHRISTI

– EDINBURG

THE STATE OF TEXAS

, Appellant,

v.

EDWARD JEROME HUFF

, Appellee.

On appeal from the 272 nd District Court

of Brazos C ounty, Texas.



## ORDER OF ABATEMENT

Before Chief Justice Contreras and Justices Long oria and Tijerina

Order Per Curiam

This cause is before the Court on its own motion

. Having reviewed the documents

on file, this Court has determined that this cause was reinstated prematurely. Our

February 23

, 2022 order of abatement remanded to the trial court to determine the

feasibility of a retrospective competency inquiry given the passage of time, availability of2 evidence, and any other pertinent considerations. See Turner v. State , 422 S.W.3d 676,

696 (Tex. C rim. App. 2013) (citing 43 G EORGE E. D IX & J OHN M. S CHMOLESKY

, T EXAS

P RACTICE : C RIMINAL P RACTICE AND P ROCEDURE § 31:81, at 89

– 90 & n.10 (3d ed. 2011)).

The trial court has complied with this directive, determining that a competency hearing is

feasible. As such, on remand, the trial court is instructed to conduct an informal inquiry

into Edward Jerome Huff’s competency to stand trial. If the informal inqui ry establishes

that there is some evidence of incompetency, the trial court shall conduct a formal

competency trial. I t is hereby ORDERED that the supplemental clerk ’ s record and the

supplemental reporter ’ s record of the trial court ’ s proceedings on remand shall be filed

with this Court on or before ninety days from the date of this order f or reinstatement of

this appeal. See Bautista v. State , 605 S.W.3d 520, 530

– 31 (Tex. App.

— Houston [14th

Dist.] 2020, no pet. )

.

We abate this appeal and remand to the trial court for proceedings consistent with

this order

.

PER CURIAM

Do not publish.

T EX

. R. A PP

. P. 47.2 ( b ).

Delivered and filed on the

25 t h day of January, 2023.
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# Final Report-Assessment of Potential Phosphate Ion-Cenmentitious Materials Interactions (NUREG/CR-6938)

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## Publication Information

**Manuscript Completed:** November 2006 **Date Published:** June 2007 

**Prepared by:** D.J. Naus, C.H. Mattus, and L.R. Dole 

Oak Ridge National Laboratory Managed by UT-Battelle, LLC P.O. Box 2008 Oak Ridge, TN 37831-6283

H. L. Graves, NRC Project Manager

**Prepared for**: Division of Fuel, Engineering and Radiological Research Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission  Washington, DC 20555-0001 

NRC Job Code N6002 

Availability Notice

## Abstract

The objectives of this limited study were to: (1) review the potential for degradation of cementitious materials due to exposure to high concentrations of phosphate ions; (2) provide an improved understanding of any significant factors that may lead to a requirement to establish exposure limits for concrete structures exposed to soils or ground waters containing high levels of phosphate ions; (3) recommend, as appropriate, whether a limitation on phosphate ion concentration in soils or ground water is required to avoid degradation of concrete structures; and (4) provide a "primer" on factors that can affect the durability of concrete materials and structures in nuclear power plants.

An assessment of the potential effects of phosphate ions on cementitious materials was made through a review of the literature, contacts with concrete research personnel, and conduct of a "bench-scale" laboratory investigation. Results of these activities indicate that: no harmful interactions occur between phosphates and cementitious materials unless phosphates are present in the form of phosphoric acid; phosphates have been incorporated into concrete as set retarders, and phosphate cements have been used for infrastructure repair; no standards or guidelines exist pertaining to applications of reinforced concrete structures in high-phosphate environments; interactions of phosphate ions and cementitious materials has not been a concern of the research community; and laboratory results indicate similar performance of specimens cured in phosphate solutions and those cured in a calcium hydroxide solution after exposure periods of up to eighteen months. Relative to the "primer," a separate NUREG report has been prepared that provides a review of pertinent factors that can affect the durability of nuclear power plant reinforced concrete structures.

Page Last Reviewed/Updated Thursday, March 25, 2021
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# Acceptance and Verification For Early Warning Fire Detection Systems (NUREG/CR-1798)

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## Publication Information

**Manuscript Completed:**May 1980

**Prepared by:** J.L. Boccio and R.E. Hall Brookhaven National Laboratory Upton, New York 11973 

I. Asp Gage-Babcock and Associates, Inc. Mount Kisco, New York 10549

NRC FIN NO. A-3335

**Prepared for:** U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under Interagency Agreement DE-ACO2-76CH00016

Availability Notice

## Abstract

This report has been written to provide an interim guide accounting for the basic factors that should be considered in formulatina a fire detection system selection criteria and the verification of such a system. The fire detection system selection criteria that is proposed here still requires a viable mix of good engineering judgement, the use of qualified investigators, and excellent reporting and administrative procedures; all of which should be coupled to the results of current research that has been discussed herein. The fire detection analysis should address five major phases required in a fire detection analysis, viz, (1) establishing area detector requirements, (2) selection of specific detector types, (3) location and spacing of detectors, (4) installation tests and maintenance, and (5) administrative controls and reporting.

Page Last Reviewed/Updated Wednesday, March 24, 2021
EXHIBIT 23.1

               CONSENT OF INDEPENDENT CERTIFIED PUBLIC ACCOUNTANTS

Janel World Trade Ltd.
150-14 132nd Avenue
Jamaica, New York 11434

Gentlemen:

We have issued our report dated  November 25, 2003  accompanying  the  financial
statements of Janel World Trade Ltd. and subsidiaries contained in the Form 10-K
under the Securities  Exchange Act of 1934, as amended. We consent to the use of
the aforementioned  report in the Form 10-K under the Securities Exchange Act of
1934,  as  amended,  and to the use of our name as it  appears in Item 9 of Form
10-K.


                                                    /S/ PARITZ & COMPANY, P.A.
                                                    ----------------------------
                                                        Paritz & Company, P.A.

Hackensack, New Jersey
December 29, 2003