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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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April 3–5, 2025
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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An Experimental Study of Meteorological Dispersion in Siting Phases II and III of the Qinshan Nuclear Power Plant
Erbang Hu, Maoshuan Zhang, Shoushu Wang, Zhanrong Gao, Rentai Yao, Naixian Pan, Jiayi Chen, Zhong Chen, Jinsong Qiao, Huaide Zhang
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 1-17
Technical Paper | Fission Reactors | doi.org/10.13182/NT98-A2905
Heat Transfer Analysis of the Passive Residual Heat Removal System in ROSA/AP600 Experiments
Taisuke Yonomoto, Yutaka Kukita, Richard R. Schultz
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 18-30
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2906
FlowAct, Flow Rate Measurements in Pipes with the Pulsed-Neutron Activation Method
Per Lindén, Gudmar Grosshög, Imre Pázsit
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 31-51
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2907
Modification of the Reflood Model in RELAP5/MOD3.1
Hae Yong Jeong, Hee Cheon No
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 52-64
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2908
Emergency Core Cooling Mode of the European Pressurized Water Reactor: The Evolution from Combined Injection to Cold-Leg Injection
Florin Curca-Tivig
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 65-81
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2909
Estimating Heat Generation Rates for Wastes Contaminated Primarily by 137Cs and 90Sr
Mark S. Jarzemba
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 82-87
Technical Paper | Reprocessing | doi.org/10.13182/NT98-A2910
Flow Barrier System for Long-Term High-Level-Waste Isolation: Experimental Results
James L. Conca, Michael J. Apted, Wei Zhou, Randolph C. Arthur, John H. Kessler
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 88-100
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2911
Assessment and Improvement of Condensation Models in RELAP5/MOD3.2
Ki Yong Choi, Hyun Sik Park, Sang Jae Kim, Hee Cheon No, Yong Seok Bang
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 103-117
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2912
Nuclear Power Plant Transient Diagnostics Using Transfer Functions as Estimators
Igor Salamun, Andrej Stritar
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 118-137
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2913
Dose-Reduction Improvements in Storage Basins of Spent Nuclear Fuel
Frank H. Huang, Francis W. Moore
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 138-146
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT98-A2914
Newly Developed Decontamination Technology Based on Gaseous Reactions Converting to Carbonyl and Fluoric Compounds
Katsuyoshi Tatenuma, Yukio Hishinuma, Satoshi Tomatsuri, Kousaburo Ohashi, Yoshiharu Usui
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 147-164
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT98-A2915
Calculations Simulating Spent-Fuel Leaching Experiments
Hilbert Christensen
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 165-174
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT98-A2916
Conceptual Design of a Californium-Based Epithermal Neutron Beam for Boron Neutron Capture Therapy Using a Subcritical Multiplying Assembly
Do Heon Kim, Jong Kyung Kim
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 175-182
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT98-A2917
Estimate of the Radiation Environment and of the Shielding Aspect for the Large Hadron Collider POINT2 Area
Galina Chabratova, Lars Leistam
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 183-191
Technical Paper | Accelerators | doi.org/10.13182/NT98-A2918
Radioactive Release and Dose Calculations for the HTR-10
Yuan-Zhong Liu
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 192-197
Technical Note | Reactor Safety | doi.org/10.13182/NT98-A2919
Criticality Studies on Molten Lead Energy Amplifiers
Akinori Oda, José M. Martinez-Val, J. Manuel Perlado
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 201-214
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2920
The Nonproliferative Light Water Thorium Reactor: A New Approach to Light Water Reactor Core Technology
Alvin Radkowsky, Alex Galperin
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 215-222
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2921
Modeling of Boiling Water Reactor Feedwater Control Algorithms
J. A. Mowrey, P. R. Boylan, S. I. Abdel-Khalik
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 223-242
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2922
A New Mechanistic Critical Heat Flux Model at Low-Pressure and Low-Flow Conditions
Kuan-Chywan Tu, Chien-Hsiung Lee, Shih-Jen Wang, Bau-Shei Pei
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 243-254
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2923
Application of Algebraic Specification to Verify the Design of Safety Logic in Nuclear Power Plants
Akira Fukumoto, Toshifumi Hayashi, Akihiko Ohsuga, Shinichi Honiden, Nobuyuki Mori
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 255-264
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2924
A High-Definition Gamma Scanning Method for the Near-Field Nondestructive Assay of Large Nuclear Waste Barrels
Chin-Jen Chang, Samim Anghaie
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 265-275
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT98-A2925
A Feasibility Study of Gross Alpha Counting in Environmental Samples Using a Superheated-Liquid-Droplet Technique
Lung Kwang Pan
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 276-283
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT98-A2926
Analysis of the Reactivity During a Pressurized Water Reactor Main-Steam-Line-Break Transient
Garry C. Gose, Thomas J. Downar, Karl O. Ott
Nuclear Technology | Volume 124 | Number 3 | December 1998 | Pages 284-290
Technical Note | Reactor Safety | doi.org/10.13182/NT98-A2927
