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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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Development of NSSS Thermal-Hydraulic Model for KNPEC-2 Simulator Using the Best-Estimate Code RETRAN-3D
Kyung-Doo Kim, Jae-Jun Jeong, Seung-Wook Lee, Myeong-Soo Lee, Jae-Seung Suh, Jin-Hyuk Hong, Yong-Kwan Lee
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 3-11
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3543
Modeling and Simulation of the ABWR with Transient Analyses for Validation of RETRAN-3D/MOD003
Michitsugu Mori
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 12-24
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3544
Benchmarking NSP Reactors with CORETRAN-01
Donald D. Hines, Rodney L. Grow, Lance J. Agee
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 25-34
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3545
Pretest Calculations of Phase A of ISP-42 (PANDA) Using the GOTHIC Containment Code and Comparison with the Experimental Results
Michele Andreani
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 35-47
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3546
Oconee Nuclear Power Station Main Steam Line Break Analysis for Steam Generator Tube Stress Evaluation
Jan S. Muransky, John G. Shatford, Craig E. Peterson, Gregg B. Swindlehurst
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 48-55
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3547
Development of Non-LOCA Safety Analysis Methodology with RETRAN-3D and VIPRE-01/K
Yo-Han Kim, Ae-Ju Cheong, Chang-Keun Yang
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 56-67
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3548
TIMCOAT: An Integrated Fuel Performance Model for Coated Particle Fuel
Jing Wang, Ronald G. Ballinger, Heather J. Maclean
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 68-96
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT04-A3549
Some Considerations on 242mAm Production in Thermal Reactors
Alessandra Cesana, Sara Tania Mongelli, Mario Terrani, Pietro Benetti, Elio Calligarich, Rinaldo Dolfini, Gian Luca Raselli
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 97-101
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT04-A3550
Independent Postclosure Performance Estimates of the Proposed Repository at Yucca Mountain
Sitakanta Mohanty, Richard Blake Codell
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 105-114
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3551
In-Drift Natural Convection Analysis of the Low-Temperature Operating Mode Design
Michael T. Itamura, Nicholas D. Francis, Jr., Stephen W. Webb, Darryl L. James
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 115-124
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3552
Multiscale Thermohydrologic Model Analyses of Heterogeneity and Thermal-Loading Factors for a Proposed Nuclear Waste Repository
Lee G. Glascoe, Thomas A. Buscheck, James Gansemer, Yunwei Sun, Kenrick Lee
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 125-137
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3553
The Impact of Preferential Flow on the Vaporization Barrier Above Waste Emplacement Drifts at Yucca Mountain, Nevada
Jens T. Birkholzer, Sumit Mukhopadhyay, Yvonne Y. W. Tsang
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 138-150
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3554
Biogeochemical Reactive Transport Model of the Redox Zone Experiment of the Äspö Hard Rock Laboratory in Sweden
Jorge Molinero-Huguet, F. Javier Samper-Calvete, Guoxiang Zhang, Changbing Yang
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 151-165
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3555
Corrosion Behavior of Waste Package and Drip Shield Materials
Gustavo A. Cragnolino, Darrell S. Dunn, C. Sean Brossia, Yi-Ming Pan, Osvaldo Pensado, Lietai Yang
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 166-173
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3556
Re-Evaluating Neptunium in Uranyl Phases Derived from Corroded Spent Fuel
Jeffrey A. Fortner, Robert J. Finch, A. Jeremy Kropf, James C. Cunnane
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 174-180
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3557
Congruent Release of Long-Lived Radionuclides from Multiple Canister Arrays
Daisuke Kawasaki, Joonhong Ahn, Paul L. Chambré, William G. Halsey
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 181-193
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3558
Role of the Bio- and Geosphere Interface on Migration Pathways for 135Cs and Ecological Effects
Anders Wörman, Björn Anders Dverstorp, Richard Andrew Klos, Shulan Xu
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 194-204
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3559
Alternative Igneous Source Term Model for Tephra Dispersal at the Yucca Mountain Repository
Richard Blake Codell
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 205-212
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3560
Smelters as Analogs for a Volcanic Eruption at Yucca Mountain
Benjamin Ross
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 213-219
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3561
Deterministic and Monte Carlo Neutron Transport Calculations of the Dounreay Fast Breeder Reactor
A. Kemal Ziver, Sabu Shahdatullah, Matthew D. Eaton, Cassiano R. E. de Oliviera, Ron T. Ackroyd, Adrian P. Umpleby, Christopher C. Pain, Antony J. H. Goddard, James Fitzpatrick
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 223-234
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3562
Validation of Simplified Evaluation Models for First Peak Power, Energy, and Total Fissions of a Criticality Accident in a Nuclear Fuel Processing Facility by TRACY Experiments
Yasushi Nomura, Hiroshi Okuno, Yoshinori Miyoshi
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 235-243
Technical Paper | Reactor Safety | doi.org/10.13182/NT04-A3563
Plutonium Management in the Medium Term
Kevin Hesketh, Gerhard Schlosser, Dieter F. Porsch, Timm Wolf, Oliver Köberl, Benoit Lance, Rakesh Chawla, Jess C. Gehin, Ron Ellis, Sadao Uchikawa, Osamu Sato, Tsutomu Okubo, Hideaki Mineo, Toru Yamamoto, Yutaka Sagayama, Enrico Sartori
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 244-258
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3564
Development and Validation of the 3-D Computational Fluid Dynamics Model for CANDU-6 Moderator Temperature Predictions
Churl Yoon, Bo Wook Rhee, Byung-Joo Min
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 259-267
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3565
The Thermal Hydraulics of Tube Support Fouling in Nuclear Steam Generators
Helena E. C. Rummens, J. T. Rogers, C. W. Turner
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 268-286
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3566
Critical Heat Flux and Onset of Nucleate Boiling Tests in a Finned Rod Bundle
Hee Taek Chae, Jong Hark Park, Heonil Kim, Soon Heung Chang
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 287-293
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3567
Experimental Investigation of Natural-Circulation Flow Behavior Under Low-Power/Low-Pressure Conditions in the Large-Scale PANDA Facility
Olivier Auban, Domenico Paladino, Robert Zboray
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 294-312
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3568
Enhanced Natural Convection in a Metal Layer Cooled by Boiling Water
Jae-Seon Cho, Kune Y. Suh, Chang-Hyun Chung, Rae-Joon Park, Sang-Baik Kim
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 313-324
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3569
RELAP5/MOD3.2 Analysis of a VVER-1000 Reactor with UO2 Fuel and Mixed-Oxide Fuel
Yassin A. Hassan, Chun Fu
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 325-334
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3570
Code-Accuracy-Based Uncertainty Estimation (CABUE) Methodology for Large-Break Loss-of-Coolant Accidents
Sang-Yong Lee, Chang-Hwan Ban
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 335-347
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3571
A Strategic Recovery of Rare-Metal Fission Products in Spent Nuclear Fuel
Yuichi Sano, Yoshihiko Shinoda, Masaki Ozawa
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 348-357
Technical Paper | Reprocessing | doi.org/10.13182/NT04-A3572
Modeling of Colloid Transport Mechanisms Facilitating Migration of Radionuclides in Fractured Media
Shih-Hai Li, Hui-Ting Yang, Chun-Ping Jen
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 358-368
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT04-A3573
Analysis of Accidents at the Pakistan Research Reactor-1 Using Proposed Mixed-Fuel (HEU and LEU) Core
Ishtiaq H. Bokhari
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 369-376
Technical Note | Fission Reactors | doi.org/10.13182/NT04-A3574
