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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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 Technology
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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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Enhanced Thermal Expansion Control Rod Drive Lines for Passive Shutdown of Fast Reactors
Martin Edelmann, Walter Baumann, Alfred Bertram, Günter Kussmaul, Walter Väth
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 3-14
Technical Paper | Special on ANP ’92 Conference / Fission Reactor | doi.org/10.13182/NT94-A34993
Negative Void Reactivity in a Large Liquid-Metal Fast Breeder Reactor with Hydrogenous Moderator (ZrH1.7) Layers
Yoshiaki Oka, Tatjana Jevremovic, Sei-ichi Koshizuka
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 15-22
Technical Paper | Special on ANP ’92 Conference / Fission Reactor | doi.org/10.13182/NT94-A34994
Comprehensive Analysis of Passive Safety Test Phase IIB in the Fast Flux Test Facility
Akira Yamaguchi, Hajime Niwa, Mitsuaki Yamaoka, Kazuyuki Tsukimori, Yoshio Shimakawa, Hisashi Ninokata, Kiyoto Aizawa
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 23-37
Technical Paper | Special on ANP ’92 Conference / Fission Reactor | doi.org/10.13182/NT94-A34995
Design Study of the Deep-Sea Reactor X
Hiromasa Iida, Yuichi Ishizaka, Yeong-Chan Kim, Chouichi Yamaguchi
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 38-48
Technical Paper | Special on ANP ’92 Conference / Fission Reactor | doi.org/10.13182/NT94-A34996
Conceptual Design Features for a Passive Light Water Cooled and Moderated Pressure Tube Reactor (PLPTR)
Jan Ru Tang, Neil E. Todreas, Michael J. Driscoll
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 49-62
Technical Paper | Special on ANP ’92 Conference / Fission Reactor | doi.org/10.13182/NT94-A34997
Reflooding of Tight Lattice Bundles
Jean-Michel Veteau, Albert Digonnet, Roger Deruaz
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 63-71
Technical Paper | Special on ANP ’92 Conference / Nuclear Reactor Safety | doi.org/10.13182/NT94-A34998
An Intelligent Man-Machine System for Future Nuclear Power Plants
Yoji Takizawa, Yoshiaki Hattori, Juichiro Itoh, Akira Fukumoto
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 72-82
Technical Paper | Special on ANP ’92 Conference / Human Factor | doi.org/10.13182/NT94-A34999
Evaluation Program of the Integrated Surveillance and Control System ISACS—An Advanced Control Room Prototype
Conny B. O. Holmstroem, Tor Endestad, Knut Follesoe, Nils T. Foerdestroemmen, Kjell Haugset, Frode Strand Volden
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 83-92
Technical Paper | Special on ANP ’92 Conference / Reactor Control | doi.org/10.13182/NT94-A35000
The Startup of the Dodewaard Natural Circulation Boiling Water Reactor—Experiences
Wim H. M. Nissen, Jaap Van Der Voet, Jadranko Karuza
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 93-102
Technical Paper | Special on ANP ’92 Conference / Nuclear Reactor Safety | doi.org/10.13182/NT107-93
Pressurized Water Reactor Steam Line Break Analysis by Means of Coupled Three-Dimensional Neutronic, Three-Dimensional Core Thermohydraulic, and Fast Running System Codes
Hyun-Jong Paik, Patrick Raymond
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 103-111
Technical Paper | Special on ANP ’92 Conference / Nuclear Reactor Safety | doi.org/10.13182/NT94-A35002
Monitoring Feedwater Flow Rate and Component Thermal Performance of Pressurized Water Reactors by Means of Artificial Neural Networks
Kadir Kavaklioglu, Belle R. Upadhyaya
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 112-123
Technical Paper | Special on ANP ’92 Conference / Reactor Control | doi.org/10.13182/NT94-A35003
Consistent Generation and Functionalization of One-Dimensional Cross Sections for TRAC-BF1
José Luis Muñoz-Cobo, Gumersindo Verdú, Claubia Pereira, Alberto Escrivá, José Ródenas, Felix Castrillo, Juan Serra
Nuclear Technology | Volume 107 | Number 2 | August 1994 | Pages 125-137
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A34983
Qualification of the Taiwan Power Company’s Pressurized Water Reactor Physics Methods Using CASMO-3/SIMULATE-3
Ping-Hue Huang, Jing-Tong Yang
Nuclear Technology | Volume 107 | Number 2 | August 1994 | Pages 138-154
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A34984
Hybrid Thermionic Space Reactors for Power and Propulsion
Sümer Şahin, Elliot B. Kennel
Nuclear Technology | Volume 107 | Number 2 | August 1994 | Pages 155-181
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A34985
A New Fuel Material for Once-Through Weapons Plutonium Burning
Hiroshi Akie, Tadasumi Muromura, Hideki Takano, Shojiro Matsuura
Nuclear Technology | Volume 107 | Number 2 | August 1994 | Pages 182-192
Technical Paper | Fission Reactor | doi.org/10.13182/NT107-182
Methods for the Determination of the In-Phase and Out-of-Phase Stability Characteristics of a Boiling Water Reactor
Tim H. J. J. Van Der Hagen, Imre Pázsit, Ola Thomson, Bengt Melkerson
Nuclear Technology | Volume 107 | Number 2 | August 1994 | Pages 193-214
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34987
Special Concrete Shield Selection Using the Analytic Hierarchy Process
Waleed H. Abulfaraj
Nuclear Technology | Volume 107 | Number 2 | August 1994 | Pages 215-226
Technical Paper | Radiation Protection | doi.org/10.13182/NT94-A34988
Parametric Study of Recriticality in a Boiling Water Reactor Severe Accident
Bassam I. Shamoun, Robert J. Witt
Nuclear Technology | Volume 107 | Number 2 | August 1994 | Pages 227-235
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34989
Noise Analysis Method for Monitoring the Moderator Temperature Coefficient of Pressurized Water Reactors: Neural Network Calibration
J. R. Thomas, Jr., Joseph T. Adams
Nuclear Technology | Volume 107 | Number 2 | August 1994 | Pages 236-240
Technical Note | Reactor Operation | doi.org/10.13182/NT94-A34990
Radiation Damage in a Rock Salt Nuclear Waste Repository
Wim J. Soppe, Jan Prij
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 243-253
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35005
Low-Level Radioactive Hanford Wastes Immobilized by Cement-Based Grouts
Frank H. Huang, Dolores E. Mitchell, John M. Conner
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 254-271
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35006
Industrial Scale Removal of Cesium with Hexacyanoferrate Exchanger—Process Development
Risto Harjula, Jukka Lehto, Esko H. Tusa, Asko Paavola
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 272-278
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35007
Industrial Scale Removal of Cesium with Hexacyanoferrate Exchanger—Process Realization and Test Run
Esko H. Tusa, Asko Paavola, Risto Harjula, Jukka Lehto
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 279-284
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35008
Criticality Data and Validation Studies of Arrays of Mixed-Oxide Fuel Pins in Aqueous and Organic Solutions
Gary R. Smolen, Sidney R. Bierman, Nobuo Fukumura
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 285-303
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT94-A35009
Criticality Data and Validation Studies of Plutonium-Uranium Nitrate Solutions in Cylindrical and Slab Geometry
Gary R. Smolen, Raymond C. Lloyd, Hideyuki Funabashi
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 304-325
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT94-A35010
Criticality Data and Validation Studies of Plutonium-Uranium Nitrate Solutions in Annular Geometry
Gary R. Smolen, Raymond C. Lloyd, Tomozo Koyama
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 326-339
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT94-A35011
Criticality Data and Validation Studies of Mixed-Oxide Fuel Pin Arrays in Pu+U+Gd Nitrate
Gary R. Smolen, Raymond C. Lloyd, Tadakuni Matsumoto
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 340-355
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT94-A35012
