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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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The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios
Charles G. Bathke, Bartley B. Ebbinghaus, Brian A. Collins, Brad W. Sleaford, Kevin R. Hase, Martin Robel, Richard K. Wallace, Keith S. Bradley, John R. Ireland, Gordon D. Jarvinen, M. W. Johnson, Andrew W. Prichard, Brian W. Smith
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 5-30
Technical Paper | Special Issue on Safeguards / Materials for Nuclear Systems | doi.org/10.13182/NT10-203
The Proliferation Resistance Debate and the Proliferation Resistance and Physical Protection Evaluation Methodology
Joseph F. Pilat
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 31-34
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-31
Proliferation Resistance and Physical Protection Evaluation Methodology: Objectives, Accomplishments, and Future Directions
Robert A. Bari
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 35-44
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-35
Elements of the Proliferation Resistance and Physical Protection Evaluation Methodology
Per F. Peterson
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 45-51
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-45
Implementation of the PR&PP Methodology: The Role of Formal Expert Elicitations
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 52-60
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-52
Implications for Advanced Safeguards Derived from a Proliferation Resistance and Physical Protection Case Study for a Generation IV Nuclear Energy System
Brian D. Boyer, Heather H. Erpenbeck, Carolynn P. Scherer
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 61-69
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-61
A Qualitative Assessment of Diversion Scenarios for an Example Sodium Fast Reactor Using the Generation IV PR&PP Methodology
Michael D. Zentner, Garill A. Coles, Ike U. Therios
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 70-75
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-70
Applying the GIF PR&PP Methodology for a Qualitative Analysis of a Misuse Scenario in a Notional Generation IV Example Sodium Fast Reactor
Giacomo G. M. Cojazzi, Guido Renda, Jor Shan Choi, Jim Hassberger
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 76-90
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-76
Proliferation Resistance of a Hypothetical Sodium Fast Reactor Under an Assumed Breakout Scenario
Jeremy J. Whitlock, Naoko Inoue, Masao Senzaki, Dennis Bley, Ed Wonder
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 91-96
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-91
INPRO Studies of Proliferation Resistance for DUPIC Fuel Cycle
Yongdeok Lee, Jung Won Lee, Joo-Hwan Park
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 97-105
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14070
Interpretation and Use of the Results of Proliferation Resistance Studies
Michael D. Zentner, George Pomeroy, Robert A. Bari, Giacomo G. M. Cojazzi, Eckhart Haas, Thomas Killeen, P. Peterson, Jeremy J. Whitlock, Edward F. Wonder
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 106-111
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14071
Challenges to Integration of Safety and Reliability with Proliferation Resistance and Physical Protection for Generation IV Nuclear Energy Systems
H. Khalil, P. F. Peterson, R. Bari, G.-L. Fiorini, T. Leahy, R. Versluis
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 112-116
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14072
Strengthening the Nonproliferation Regime with Risk Acceptance Criteria
Edoardo Cavalieri d'Oro, Michael W. Golay
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 117-128
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14073
Informing Nuclear Energy Systems with Proliferation Risk
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 129-142
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14074
Integrating Safeguards and Security into Nuclear Facility Design
T. Bjornard, J. Morgan
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 143-149
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14075
Safety, Security, and Safeguards by Design: An Industrial Approach
Marius Stein, Massimo Morichi
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 150-155
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14076
Open Source Information Acquisition and Analysis in the International Atomic Energy Agency Department of Safeguards
Michael Barletta, Nicholas Zarimpas, Ryszard Zarucki
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 156-159
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14077
Benchmarked, Three-Dimensional Antineutrino Source Term Calculations of Light Water Reactors for Nonproliferation Applications
Elanchezhian Somasundaram, Todd S. Palmer, Alexey I. Soldatov
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 160-168
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14078
Generalized Perturbation Theory-Free Sensitivity Analysis for Eigenvalue Problems
Chris Kennedy, Cristian Rabiti, Hany Abdel-Khalik
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 169-179
Technical Paper | Fission Reactors | doi.org/10.13182/NT179-169
Effects of Fuel Relocation for Transport Casks
Alan H. Wells, Albert J. Machiels
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 180-188
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-A14090
Fabrication of (U-Pu) Mixed-Oxide Fuel for Pressurized Heavy Water Reactors
J. P. Panakkal, M. Afzal, R. B. Bhatt, A. Prakash, A. K. Mishra, S. Kumar, H. S. Kamath
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 189-195
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14091
Determination of the Plutonium Mass and Curium Ratio of Spent Fuel Assemblies for Input Nuclear Material Accountancy of Pyroprocessing, and Analysis of Their Errors
Tae-Hoon Lee, Young-Soo Kim, Tae-Je Kwon, Hee-Sung Shin, Ho-Dong Kim
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 196-204
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT11-77
Water Chemistry in a Supercritical Water-Cooled Pressure Tube Reactor
D. Guzonas, F. Brosseau, P. Tremaine, J. Meesungnoen, J.-P. Jay-Gerin
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 205-219
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A14093
Pyrochemical Reprocessing Tests to Collect Uranium Metal from Simulated Spent Oxide Fuel
Yoshiharu Sakamura, Masaaki Akagi
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 220-233
Technical Paper | Reprocessing | doi.org/10.13182/NT179-220
Theoretical Maximum Efficiencies of Optimized Slab and Spherical Betavoltaic Systems Utilizing Sulfur-35, Strontium-90, and Yttrium-90
Kyuhak Oh, Mark A. Prelas, Jason B. Rothenberger, Eric D. Lukosi, Jeho Jeong, Daniel E. Montenegro, Robert J. Schott, Charles L. Weaver, Denis A. Wisniewski
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 234-242
Technical Paper | Radioisotopes | doi.org/10.13182/NT12-A14095
Theoretical Maximum Efficiency for a Linearly Graded Alphavoltaic Nuclear Battery
Kyuhak Oh, Mark A. Prelas, Eric D. Lukosi, Jason B. Rothenberger, Robert J. Schott, Charles L. Weaver, Daniel E. Montenegro, Denis A. Wisniewski
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 243-249
Technical Paper | Radioisotopes | doi.org/10.13182/NT12-A14096
Criticality Evaluation for the Monju Restart Core
Taira Hazama, Akihiro Kitano, Y. Kishimoto
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 250-265
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14097
Control Rod Worth Evaluation for the Monju Restart Core
Kazuya Takano, Masahiro Fukushima, Taira Hazama, Takayuki Suzuki
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 266-285
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14098
Isothermal Temperature Coefficient Evaluation for the Monju Restart Core
Tetsuya Mouri, Shuhei Maruyama, Taira Hazama, Takayuki Suzuki
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 286-307
Technical Note | Fission Reactors | doi.org/10.13182/NT12-A14099
Design Study to Increase Plutonium Conversion Ratio of HC-FLWR Core
Akifumi Yamaji, Yoshihiro Nakano, Sadao Uchikawa, Tsutomu Okubo
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 309-322
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT12-A14165
Propagation of 235,236,238U and 239Pu Nuclear Data Uncertainties for a Typical PWR Fuel Element
D. Rochman, A. J. Koning, D. F. Da Cruz
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 323-338
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT11-61
Reactor Loose Part Damage Assessments on Steam Generator Tube Sheets
W. Cyrus Proctor, J. Michael Doster
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 339-359
Technical Paper | Fission Reactors/Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A14167
Evaluation of JSFR Key Technologies
Yoshitaka Chikazawa, Kazumi Aoto, Hiroki Hayafune, Shoji Kotake, Yushi Ohno, Takaya Ito, Mikio Toda
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 360-373
Technical Paper | Fission Reactors | doi.org/10.13182/NT179-360
An Examination of Simplification and Uncertainty on Material Attractiveness Evaluation for Proliferation Resistance Assessment
Steven E. Skutnik, Man-Sung Yim
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 374-381
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14169
Analysis of BR2 Loss-of-Flow Tests C and F
Constantine P. Tzanos, B. Dionne
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 382-391
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A14170
An Algorithmic Approach for RELAP5/MOD3 Reactivity Insertion Analysis in Research Reactors
S. Chatzidakis, A. Ikonomopoulos, M. Alamaniotis
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 392-406
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A14171
Studies on Separation of Minor Actinides from Lanthanides from High Level Waste by Extraction Chromatography Using 2,6-Bistriazinyl Pyridine
P. Deepika, K. N. Sabharwal, T. G. Srinivasan, P. R. Vasudeva Rao
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 407-416
Technical Paper | Reprocessing | doi.org/10.13182/NT12-A14172
In-Situ Creep Testing Capability for the Advanced Test Reactor
Bong Goo Kim, Joy L. Rempe, Darrell L. Knudson, Keith G. Condie, Bulent H. Sencer
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 417-428
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT12-A14173
Hemispherical Total Emissivity of Potential Structural Materials for Very High Temperature Reactor Systems: Haynes 230
Raymond K. Maynard, Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Dabir S. Viswanath, Sudarshan K. Loyalka
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 429-438
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT11-5
