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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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A Knowledge-Based System for Power Maneuver Planning for Boiling Water Reactors
Mitsuo Kinoshita, Takaharu Fukuzaki, Akira Nishimura, Yukihisa Fukasawa, Tsutomu Matsuki
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 1-10
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A35528
A New Boiling Water Reactor Core Concept for a Next-Generation Light Water Reactor
Junichi Yamashita, Akira Nishimura, Takaaki Mochida, Osamu Yokomizo
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 11-19
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A35529
Development of a High-Conversion Boiling Water Reactor
Junichi Yamashita, Takaaki Mochida
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 20-28
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A35530
Results of Postirradiation Examination of the In-Pile Blockage Experiments Mol-7C/4 and Mol-7C/5
P. Weimar, Karl Schleisiek
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 29-36
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A35531
Safety Analysis of Depressurization Accidents in a Medium-Sized High-Temperature Gas Reactor
Shlomo Ron, Judah Tzoref
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 37-49
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A35532
Assessment of Gamma Fields Inside Buildings in an Urban Area Resulting from External Radionuclide Deposition
O. Graf, A. Bayer
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 50-71
Technical Paper | Nuclear Safety | doi.org/10.13182/NT91-A35533
Fabrication Experience of AI-233U and Al-Pu Plate Fuel for the Purnima III and Kamini Research Reactors
C. Ganguly, G. J. Prasad, K. N. Mahule, J. K. Ghosh, K. V. J. Asari, K. N. P. Chandrasekharan, S. Muralidhar, T. S. Balan, P. R. Roy
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 72-83
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A35534
U(IV) and U(VI) Extraction Behavior in Pulsed Columns During Off-Standard Operation
Kenzo Munakata, Masahiro Nabeshima
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 84-95
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT91-A35535
Vaporization of Strontium, Barium, Lanthanum, and Uranium from Mixtures of Urania, Zirconia, Steel, and Concretes at 2150 and 2400 K
Michael F. Roche, Leonard Leibowitz, Jack L. Settle, Carl E. Johnson, Richard C. Vogel, Robert L. Ritzman
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 96-116
Technical Paper | Material | doi.org/10.13182/NT91-A35536
Finite Element Stress Analysis for Coated Particle Fuel Modeling Under Normal Operating Conditions
Ralph G. Bennett
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 117-122
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A35537
Steady-State Simulations of a 30-Tube Once-Through Steam Generator with the RELAP5/MOD3 and RELAP5/MOD2 Computer Codes
Yassin A. Hassan, Parvez Salim
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 123-128
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A35538
A “Nonproliferating” Nuclear Fuel for Light Water Reactors
Yigal Ronen, Yehoshua Kimhi
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 133-138
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34599
Simulation of the Primary-Secondary Leak Experiment of IAEA’ Third Standard Problem Exercise Using the RELAP5/MOD2 and RELAP5/MOD3 Computer Codes
Y. A. Hassan, Parvez Salim
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 139-146
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34600
N Reactor Level III Probabilistic Risk Assessment Using NUREG-1150 Methods
Oliver S. Wang, Garill A. Coles, John E. Kelly, Thomas B. Powers, Thomas E. Rainey, Michael D. Zentner, Gregory D. Wyss, David M. Kunsman, LeAnn Adams Miller, Timothy A. Wheeler, Jeremy L. Sprung, Allen L. Camp
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 147-168
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34601
Studies of the Preparation of Thoria and Thoria-Urania Microspheres Using an Internal Gelation Process
N. Kumar, R. K. Sharma, V. R. Ganatra, S. K. Mukerjee, V. N. Vaidya, D. D. Sood
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 169-177
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34602
In Situ Vitrification of Soils Containing Various Metals
James L. Buelt, Richard K. Farnsworth
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 178-184
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT91-A34603
Properties of a Radioactive Waste Pellet Package Using Cement-Glass
Kiyomi Funabashi, Koichi Chino, Makoto Kikuchi, Susumu Horiuchi, Hiroyuki Tsuchiya
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 185-191
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT91-A34604
The Equilibrium Concept—An Extended Approach to Assess Long-Term Radionuclide Release from Repositories
Rainer Köster, Günter Rudolph
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 192-201
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT91-A34605
Results of 0.5% Hot-Leg Break Loss-of-Coolant Accident Experiments at ROSA-IV/LSTF: The Effect of Break Orientation
Hideaki Asaka, Yutaka Kukita, Taisuke Yonomoto, Kanji Tasaka
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 202-214
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34606
Influence of Secondary System Conditions on Steam Generator U-Tube Flow Distribution During Single-Phase Natural Circulation
Alessandro Annunziato
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 215-228
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34607
A Water Level-Initiated Decay Energy Cooling System
Charles W. Forsberg
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 229-235
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34608
Study of Coolant Activation and Dose Rates with Flow Rate and Power Perturbations in Pool-Type Research Reactors
Nasir M. Mirza, Sikander M. Mirza, N. Ahmad
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 237-247
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34586
Evaluation of a Dilute Chemical Decontaminant for Pressurized Heavy Water Reactors
S. Velmurugan, S. V. Narasimhan, P. K. Mathur, K. S. Venkateswarlu
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 248-258
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-248
Estimates of Rupture Probabilities for Nuclear Power Plant Components: Expert Judgment Elicitation
Truong V. Vo, Patrick G. Heasler, Steven R. Doctor, Frederic A. Simonen, Bryan F. Gore
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 259-271
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34588
The Response of Ex-Core Neutron Detectors to Large- and Small-Break Loss-of-Coolant Accidents in Pressurized Water Reactors
E. Wilson Okyere, Anthony J. Baratta, William A. Jester
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 272-289
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34589
Temporary Core Liquid Level Depression During a Cold-Leg Small-Break Loss-of-Coolant Accident: The Effect of Break Size and Power Level
Yasuo Koizumi, Hiroshige Kumamaru, Yuichi Mimura+, Yutaka Kukita, Kanji Tasaka†
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 290-301
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34590
Quantitative Fuel Motion Determination with the CABRI Fast Neutron Hodoscope: Evaluation Methods and Results
Kurt Baumung, Gérard Augier
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 302-313
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34591
A Model to Predict the Ultimate Failure of Coated Fuel Particles During Core Heatup Events
Toru Ogawa, Kazuo Minato, Kousaku Fukuda, Masami Numata, Hideshi Miyanishi, Hajime Sekino, Hideo Matsushima, Tadaharu Itoh, Shigeo Kado, Ishio Takahashi
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 314-322
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34592
High-Temperature Reactor Fuel Fission Product Release and Distribution at 1600 to 1800°C
Werner Schenk, Heinz Nabielek
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 323-336
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-3-323
Isotope Separation by Chemical Exchange: A Computer Simulation
Heinrich R. Obermoller, David A. White
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 337-345
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT91-A34594
Neutron Effects on Borated Stainless Steel
S. E. Soliman, D. L. Youchison, A. J. Baratta, T. A. Balliett
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 346-352
Technical Paper | Material | doi.org/10.13182/NT91-A34595
Operating Margin of Soviet RBMK-1000 Nuclear Power Reactors
James M. Adams, Lawrence E. Hochreiter, Gordon E. Robinson
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 353-360
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34596
