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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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Validation of MCNP for RBMK Criticality Calculations
Dietmar Behrens, Sebastian Meyer, Dieter Von Ehrenstein, Richard Donderer, Otfried Schumacher, Galina Davydova, Alexander Krayushkin
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 1-11
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35219
Determination of Core Design Thermal Safety Limits for a Two-Loop Pressurized Water Reactor
Venceslav Kostadinov
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 12-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35220
Fission Product Releases at Severe Light Water Reactor Accident Conditions: ORNL/CEA Measurements Versus Calculations
Bernard André, Gérard Ducros, Jean Pierre Lévêque, Morris F. Osborne, Richard A. Lorenz, Denis Maro
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 23-50
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35221
Analysis of Loss-of-Coolant Accidents in the High-Flux Isotope Reactor
Mark W. Wendel, David G. Morris, Paul T. Williams
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 51-67
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35222
A Model of Vented Hydrogen Deflagrations in a Containment
Matthias Heitsch
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 68-76
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35223
Protection from Radioaerosols and Volatile Radionuclides
Nikolai B. Mikheev, Sergei A. Kulyukhin, Alla N. Kamenskaya, Igor’ A. Rumer
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 77-83
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35224
A Comparative Risk Assessment for the Russian V213 Power Reactor
Theron D. Marshall, Robert W. Hockenbury, John A. Honey, Lee C. CadWallader
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 84-96
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35225
Some Computations in Planning Reconstitution of a 500-MW(electric) Fast Breeder Reactor (Metallic) Fuel by Electrorefining
H. P. Nawada, N. P. Bhat, G. R. Balasubramanian
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 97-110
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35226
Structural Integrity of Spent Nuclear Fuel Storage Casks Subjected to Drop
John R. Stokley, David H. Williamson
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 111-121
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35227
Radioiodine Deposition Losses from Sample Air Containing Particulate and Gaseous Iodine in Nuclear Reactor Sample Lines
Byung-Soo Lee, William A. Jester
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 122-134
Technical Paper | Material | doi.org/10.13182/NT96-A35228
An Analytical Approach to Transient Room Temperature Analysis
T. Paul Yilmaz, William B. Paschal
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 135-140
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35229
On the Subcooled Critical Flow Model in RELAP5/MOD3
W. S. Yeung, J. Shirkov
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 141-145
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35230
Verification and Implications of the Multiple-Pin Treatment in the SASSYS-1 Liquid-Metal Reactor Systems Analysis Code
Floyd E. Dunn
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 147-157
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35245
Preliminary Accident Analysis to Support a Passive Depressurization System Design
Roberto Lenti, Luigi Mansani, Gianfranco Saiu
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 158-168
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35246
A Probabilistic Risk Assessment—Related Methodology to Support Performance-Based Regulation Within the Nuclear Power Industry
Renée M. Dubord, Michael W. Golay, Norman C. Rasmussen
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 169-178
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35247
Risk Assessment for Spent-Fuel Pool Cooling at Boiling Water Reactors
Truong V. Vo, Timothy M. Mitts, Tyrone R. Blackburn, Hanh K. Phan
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 179-193
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35248
Preparation of Transuranium Fuel and Target Materials for the Transmutation of Actinides by Gel Coconversion
Guido Ledergerber, Franz Ingold, Richard W. Stratton, Hans-Peter Alder, Claude Prunier, Dominique Warin, Mireille Bauer
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 194-204
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35249
Computer Modeling of Single-Cell and Multicell Thermionic Fuel Elements
Jeffrey W. Dickinson, Andrew C. Klein
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 205-223
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35250
Criticality Safety Strategy and Analysis Summary for the Fuel Cycle Facility Electrorefiner at Argonne National Laboratory West
Robert D. Mariani, Robert W. Benedict, Richard M. Lell, Ronald B. Turski, Edward K. Fujita
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 224-234
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35251
Near-Field and Far-Field Migration of Radionuclides from a Shallow Land Burial Facility
R. N. Nair, T. M. Krishnamoorthy
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 235-245
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35252
Formation of Hot Particles During the Chernobyl Nuclear Power Plant Accident
Valery A. Kashparov, Yuri A. Ivanov, Sergey I. Zvarisch, Valentin P. Protsak, Yuri V. Khomutinin, Alexander D. Kurepin, Edvard M. Pazukhin
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 246-253
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35253
Investigation of 14C Release in an Engineered Low-Level Waste Disposal Facility
Man-Sung Yim, Scott A. Simonson, Terry M. Sullivan
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 254-271
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35254
UO2 Core Design of a Direct-Cycle Fast Converter Reactor Cooled by Supercritical Water
Tatjana Jevremovic, Yoshiaki Oka, Sei-Ichi Koshizuka
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 273-284
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35232
Response Analysis of Electromagnetic Flowmeter
Akira Endou
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 285-291
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35233
Fuel Channel Analysis for a Large-Break Loss-of-Coolant Accident in a Canada Deuterium Uranium Reactor Loaded with CANFLEX Fuel Bundles
Dirk J. Oh, Hong S. Lim, Myeong Y. Ohn, Kang M. Lee, Ho C. Suk
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 292-307
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35234
Operating Experience with the Multienrichment Initial Core of the Boiling Water Reactor Kashiwazaki-Kariwa Unit 5
Takaaki Mochida, Mitsunari Nakamura, Jun-Ichi Yamashita, Hiromi Maruyama, Sakae Muto, Shigeru Kasai
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 308-317
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35235
Recent Results on the Solubility of Uranium and Plutonium in Savannah River Site Waste Supernate
David T. Hobbs, David G. Karraker
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 318-324
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35236
The Effect of Geological Parameters on Radiation Damage in Rock Salt: Application to Rock Salt Repositories
Carles De Las Cuevas, Lourdes Miralles, Juan José Pueyo
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 325-336
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35237
Decontamination Flange Film Characterization for a Boiling Water Reactor Under Hydrogen Water Chemistry
V. F. Baston, M. F. Garbauskas, J. Bozeman
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 337-350
Technical Paper | Material | doi.org/10.13182/NT96-A35238
Pool Boiling from Downward-Facing Curved Surfaces: Effects of Radius of Curvature and Edge Angle
Mohamed S. El-Genk, Cheng Gao
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 351-364
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35239
TRIGA Spent-Fuel Storage Criticality Analysis
Matjaž Ravnik, Bogdan Glumac
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 365-372
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT96-A35240
Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence
John C. Wagner, Alireza Haghighat, Bojan G. Petrovic
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 373-398
Technical Paper | Radiation Protection | doi.org/10.13182/NT96-A35241
Experimental Investigation of Coupled Natural Circulation Loops
Arafah E. Ghoneimy, Richard S. Dougall
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 399-403
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35242
Analysis of Routine Radiological Measurements in a Nuclear Power Plant
V. K. Gupta, Sunil Sunny
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 404-412
Technical Note | Radiation Protection | doi.org/10.13182/NT96-A35243
