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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
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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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Experimental and Analytical Assessment of Natural Circulation Interruption Phenomenon in the LSTF and PKL Test Facilities
A. Bousbia Salah, J. Vlassenbroeck, H. Austregesilo
Nuclear Technology | Volume 192 | Number 1 | October 2015 | Pages 1-10
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-51
Deformed Core Reactivity Evaluation with Mesh Projection–Based Method
M. Gentili, B. Fontaine, G. Rimpault
Nuclear Technology | Volume 192 | Number 1 | October 2015 | Pages 11-24
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-123
Comparison of Hydrogen Generation Rate Between CORA-13 Test and MELCOR Simulation: Clad Solid-Phase Oxidation Models Using Self-Developed Code MYCOAC
Jun Wang, Michael L. Corradini, Troy Haskin, Yapei Zhang, Qing Lu, Wenxi Tian, Guanghui Su, Suizheng Qiu
Nuclear Technology | Volume 192 | Number 1 | October 2015 | Pages 25-34
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-96
Study on Chemical Interaction of U3Si2 Dispersoid and Aluminum Matrix in Plate Fuel Elements and Its Influence on the Mechanical Properties
V. P. Sinha, D. Kohli, R. Rakesh, P. V. Thakar, A. Kumar
Nuclear Technology | Volume 192 | Number 1 | October 2015 | Pages 35-47
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-59
Advanced Nuclear Open Air-Brayton Cycles for Highly Efficient Power Conversion
Bahman Zohuri, Patrick J. McDaniel, Cassiano R. R. De Oliveira
Nuclear Technology | Volume 192 | Number 1 | October 2015 | Pages 48-60
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-42
Artificial Neural Networks and Chaos Dynamics for Radiation Signal Encryption
S. Chatzidakis, P. T. Forsberg, L. H. Tsoukalas
Nuclear Technology | Volume 192 | Number 1 | October 2015 | Pages 61-73
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT14-112
Methodology and Software for Gross Defect Detection of Spent Nuclear Fuel at the Atucha-I Reactor
Shivakumar Sitaraman, Young S. Ham, Narek Gharibyan, Orpet J. M. Peixoto, Gustavo Diaz
Nuclear Technology | Volume 192 | Number 1 | October 2015 | Pages 74-83
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT14-63
Calibration of the Conical Array for the Facility for Antiproton and Ion Research Using the Probability Correction Approach
Sherif S. Nafee
Nuclear Technology | Volume 192 | Number 1 | October 2015 | Pages 84-90
Technical Note | Radiation Transport and Protection | doi.org/10.13182/NT14-89
COSI6: A Tool for Nuclear Transition Scenario Studies and Application to SFR Deployment Scenarios with Minor Actinide Transmutation
C. Coquelet-Pascal, M. Tiphine, G. Krivtchik, D. Freynet, C. Cany, R. Eschbach, C. Chabert
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 91-110
Technical Paper | Fission Reactors | doi.org/10.13182/NT15-20
Severe External Hazard on Hypothetical JSFR in 2010
Yoshitaka Chikazawa, Atsushi Katoh, Hiroyuki Hayafune, Yoshio Shimakawa, Yoshio Kamishima
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 111-124
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-151
Fuel Assembly Verification for Safe Operation of Nuclear Power Plants
Hitesh Rajput, Tanmoy Som, Soumitra Kar
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 125-132
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-154
Development of a SPECT System for Industrial Process Flow Measurement Using Diverging Collimators
Jang-Guen Park, Sung-Hee Jung, Jong Bum Kim, Jinho Moon, Chan Hyeong Kim
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 133-141
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT15-16
Dependence of Fire Time of Concern on Location of a One-Assembly Transport Package
Ketan Mittal, Ahti Suo-Anttila, Miles Greiner
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 142-154
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT14-156
Study on the Behavior of Radiolytically Produced Hydrogen in a High-Level Liquid Waste Tank of a Reprocessing Plant: Comparison Between Actual and Simulated Solutions
Hiroshi Kinuhata, Masahiko Yamamoto, Shigeo Taguchi, Naoki Surugaya, Soichi Sato, Takashi Kodama, Yoshikazu Tamauchi, Yuki Shibata, Kiyoshi Anzai, Shingo Matsuoka
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 155-159
Technical Paper | Reprocessing | doi.org/10.13182/NT15-15
Uranous Nitrate Preparation by Catalytic Reduction: A Pilot Plant Facility
Avinash Sahu, Tessy Vincent
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 160-164
Technical Paper | Reprocessing | doi.org/10.13182/NT15-9
Application of a One-Dimensional Transient Electrorefiner Model to Predict Partitioning of Plutonium from Curium in a Pyrochemical Spent Fuel Treatment Process
M. Gonzalez, L. Hansen, D. Rappleye, R. Cumberland, M. F. Simpson
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 165-171
Technical Paper | Reprocessing | doi.org/10.13182/NT15-28
Maximum Likelihood Estimation of Neutron Source Location
Jian-Yu Zhu, Hao-Wei Dai, Wen-Xiong Xie
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 172-180
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT14-115
Neutron Characteristics of Solid Targets in Accelerator-Driven System with 100-MeV Protons at Kyoto University Critical Assembly
Cheol Ho Pyeon, Hiroyuki Nakano, Masao Yamanaka, Takahiro Yagi, Tsuyoshi Misawa
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 181-190
Technical Paper | Accelerators | doi.org/10.13182/NT14-111
Optimal Shielding Design for Minimum Materials Cost or Mass
Robert D. Woolley
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 191-207
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT14-133
Radiation Protection Study for the First Korea Heavy-Ion Medical Accelerator Facility
Oyeon Kum, Seung Uk Heo, Sang Hyoun Choi, Yongkeun Song, Sung-Ho Cho
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 208-214
Technical Paper | Accelerators | doi.org/10.13182/NT14-121
Design and Performance Test of Photosensitive Glass–Based Nonfocused X-Ray Antiscattering Grid by Using MCNP Simulation
Jun Woo Bae, Hee Reyoung Kim
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 215-221
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT14-131
Experiment Design of Secondary Neutron and Charged-Particle Measurement with Stopping Targets Bombarded by 100 and 230 MeV/amu 4He Ions
Pi-En Tsai, Lawrence H. Heilbronn
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 222-231
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT14-130
Enhancements to the MCNP6 Background Source
Garrett E. McMath, Gregg W. McKinney
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 232-239
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT14-134
Computational Assessment of Naturally Occurring Neutron and Photon Background Radiation Produced by Extraterrestrial Sources
Thomas M. Miller, Wouter C. de Wet, Bruce W. Patton
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 240-249
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT14-153
Testing the Delayed Gamma Capability in MCNP6
R. A. Weldon, Jr., M. L. Fensin, G. W. McKinney
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 250-258
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT14-127
Analog Neutron Transport for Nuclear Instrumentation Applications with the Monte Carlo Code TRIPOLI-4
O. Petit, E. Dumonteil
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 259-263
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT14-128
Enhanced Hybrid Diffusion-Transport Spatial Homogenization Method
Gabriel Kooreman, Farzad Rahnema
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 264-277
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT14-150
Activation Neutronics for a Swiss Pressurized Water Reactor
Manuel Pantelias, Benjamin Volmert
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 278-285
Technical Paper | Nuclear Plant Operations and Controls | doi.org/10.13182/NT15-13
The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation
Ahmad M. Ibrahim, Douglas E. Peplow, Robert E. Grove, Joshua L. Peterson, Seth R. Johnson
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 286-298
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT15-1
Radiation Mapping at JET and ITER Using Advanced Computational Acceleration Techniques and Tools
Jonathan Naish, Frances Fox, Zamir Ghani, Michael Loughlin, Lee Packer, Andrew Turner
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 299-307
Technical Paper | Accelerators | doi.org/10.13182/NT14-132
Development of the Standalone Package for Enhanced Estimation of Dose Distribution for Space Radiation Applications
Wouter C. de Wet, Lawrence W. Townsend, X. George Xu, Whitney J. Smith
Nuclear Technology | Volume 192 | Number 3 | December 2015 | Pages 308-313
Technical Note | Radiation Biology | doi.org/10.13182/NT15-21
