INL RESEARCH & DEVELOPMENT

Comparison of computer simulation and experimental validation of accidental drop event at very high 

strain in support of spent nuclear fuel canister development.

Materials Validation Coatings

Corrosion

Fracture and Mechanical Testing

High Temperature Mechanical 

Properties

Hydrogen Production and Storage 

Materials

Hydrogen Separation Materials

Irradiation

Materials Validation

Microstructure and Physical Properties

Modeling

Neutron Radiography

Nondestructive Evaluation

Post-irradiation Examination

Synthesis and Processing of Novel 

Materials

Welding and Joining

X-Ray Radiography

Capabilities/Facilities

Materials science, 

materials engineering, welding 

engineering, high temperature materials testing, high 

temperature material property 

measurements, codes and 

standards, and quality assurance. Drop weight tower and 

drop pad impact facilities; 

laser flash thermal property 

measurement system, vibration/shake tables. High 

temperature specialized heater 

development, fabrication and 

testing.

Materials

Nickel-based alloys, stainless steels, oxide dispersion 

strengthened alloys, ferritic/

martensitic alloys, advanced 

intermetallics, construction 

materials, and fuel materials. 

Depleted uranium dioxide, 

thorium dioxide, and non-radioactive ceramic materials.

Scientific/Engineering 

Issues

Data developed in literature searches and scientific 

investigations is evaluated 

and applied to the design 

and construction of nuclear 

systems. Materials engineering support is provided for 

development and application of specifications for 

fabrication of nuclear system 

components and specialized 

instrumentation. Material and 

structural response to tension, 

bending, shear and combinations of load when subjected 

to impact are investigated. 

High temperature laboratory 

equipment is used to obtain 

key insights about materials 

compatibility, interactions and 

instrumentation survivability 

under thermal cycling and 

high temperatures.

Staff

E.L. Shaber, R.E. Mizia, 

B.C. Norby, P.K. Nagata, 

W.K. Sowder, A.D. Watkins, 

H.B. Smartt, P.A. Lessing, 

P. J. Pinhero, T.E. Lister, 

T.E. Rahl, D.K. Morton, 

J.L. Rempe, K.G. Condie, 

D.L. Knudson, S.D. Snow, 

R.K. Blandford, M.E. Nitzel, 

W.R. Richins, J.L. Rempe, 

K.G. Condie, D.L. Knudson, 

C.M. Stoots, P. A. Demkowicz, L.J. Siefken, E.P. 

Loewen, and G.L. Hawkes.

Recent Projects

• Neutron absorbing alloy 

development, corrosion 

science, and welding engineering for Yucca Mountain Repository

• Design and testing of 

specialized in-pile instrumentation for measuring 

temperature, thermal conductivity, and deformation

• Development and evaluation of corrosion-resistant 

coatings for in-pile applications

• Materials and welding 

engineering support for 

INL nuclear fuel and waste 

treatment facilities such 

as the NWCF and FAST 

facilities

• Determination of DOE 

spent nuclear fuel canister 

response to accidential 

drop loads

• High temperature heater 

development for testing 

with depleted uranium 

dioxide, Japanese Nuclear 

Power Engineering Corporation, ~$1.0M/year

Continued on back
INL RESEARCH & DEVELOPMENT

05-GA50193-40

Continued from front

• Development and assessment of in-vessel core 

catcher for advanced high 

power light water reactors, 

DOE International Nuclear 

Energy Research Initiative, 

$400 K/year

Collaborations

• Sandia National Laboratory and Lehigh University 

for the development of the 

advanced neutron absorbing alloys

• Pennsylvania State University, Prof. F.B. Cheung, InVessel Retention Strategies 

for High Power Reactors

• 1999 and 2004 drop testing with Sandia Nationial 

Laboratories

Publications

“Microelectrochemical Investigation of Gadolinium Rich 

Second Phases in a Ni-CrMo-Gd Alloy,” P.J. Pinhero, 

T.E. Lister and R.E. Mizia, 

paper accepted, Corrosion 

2004, NACE International, 

Houston, TX.

“Critical Experiment Analysis of a Neutron Absorbing 

Nickel-Chromium-Molybdenum-Gadolinium Alloy Being 

Considered for the Disposal 

of Spent Nuclear Fuel,” 

D.J. Loaiza, R. Sanchez, 

G. Wachs and R.E. Mizia, 

to be published, Journal of 

Nuclear Materials Management, Institute of Nuclear 

Materials Management.

“Development of a Corrosion 

Resistant, Neutron Absorbing Structural Material,” W.L. 

Hurt, R.E. Mizia, T.E. Lister, 

P.J. Pinhero, C.V. Robino 

and J.N. Dupont, Paper #165, 

Institute of Nuclear Materials Management 44th Annual 

Meeting, July 13-17, 2003, 

Phoenix, AZ.

“Microstructure and Corrosion Performance of a Neutron Absorbing Ni-Cr-Mo-Gd 

Alloy,” R.E. Mizia, P.J. Pinhero, T.E. Lister, J.N. DuPont 

and C.V. Robino, Paper #679, 

Corrosion 2003, NACE International, Houston, TX.

“Development of Gd-Enriched Alloys for Spent 

Nuclear Fuel Applications, 

Part 1: Preliminary Characterization of Small Scale GdEnriched Stainless Steels,” 

J.N. DuPont, C.V. Robino and 

R.E. Mizia, Journal of Materials Engineering and Performance, Vol. 12, no. 2, 2003.

“Corium Retention For High 

Power Reactors By An In-vessel Core Catcher In Combination With External Reactor 

Vessel Cooling,” Nuclear 

Engineering and Design, J. 

Rempe, et al., accepted for 

publication. 

“Conceptual Design of an Invessel Core Catcher,” J. Rempe, D. Knudson, K. Condie, 

K.Y. Suh, F.B. Cheung, and 

S.B. Kim, Nuclear Engineering and Design, Nuclear 

Engineering, 230 (2004) 

311-335.

“Development of an Enhanced In-Vessel Core 

Catcher for Improving IVR 

Margins,” J.L. Rempe, D.L. 

Knudson, K.G. Condie, 

K.Y. Suh, F.-B. Cheung, and 

S.-B. Kim, Nuclear Technology, Invited paper for the Tenth 

International Topical Meeting 

on Nuclear Reactor Thermal 

Hydraulics Special Edition, to 

be published.

“High Temperature Thermocouples for In-Pile Applications,” J.L. Rempe and 

S.C. Wilkings, to be presented 

at the 11th International 

Topical Meeting on Nuclear 

Reactor Thermal-Hydraulics 

Popesʼ Palace Conference 

Center, Avignon, France, 

October 2-6, 2005.

“Preventing Failure in Spent 

Nuclear Fuel Canisters,” 

R.K. Blandford, D.K. Morton, 

T.E. Rahl, and S.D. Snow, 

American Society of Materials, Practical Failure Analysis, 

Vol. 3, Issue 4, pp. 43-49, 

August 2003.

“Preliminary Elevated Strain 

Rate Material Testing to Support Accidental Drop Analysis of Radioactive Material 

Containers,” S.D. Snow, D.K. 

Morton, T.E. Rahl, R.K. 

Blandford, and T.J. Hill, 

ASME Pressure Vessels 

& Piping Conference, San 

Diego, CA, ASME PVP-Vol. 

483, pp. 197-201, July 2004.

“Impact Testing of Stainless 

Steel Materials,” R.K. Blandford, D.K. Morton, T.E. 

Rahl, and S.D. Smow, ASME 

Pressure Vessels & Piping 

Conference, Denver, CO, to 

be presented, July 2005.

“Drop Testing of DOE Spent 

Nuclear Fuel Canisters,” 

S.D. Snow, D.K. Morton, 

T.E. Rahl, R.K. Blandford, 

and T.E. Hill, ASME Pressure 

Vessels & Piping Conference, 

Denver, CO, to be presented 

July 2005.

For more information

INL is a U.S. Department of Energy 

national laboratory operated by 

Battelle Energy Alliance

Richard N. Wright, Ph.D.

(208) 526-6127

Richard.Wright@inl.gov

Douglas C. Crawford, Ph.D.

(208) 533-7456

Douglas.Crawford@inl.gov

www.inl.gov/envenergyscience/materials