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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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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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Point Beach Nuclear Plant Secondary In-Service Inspection Project and Badness Factor Program
Ronald R. Winget
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 7-11
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34222
Design and Development of a Personal-Computer-Based Reactivity Meter for a Research Reactor
Stephen E. Binney, Alla J. M. Bakir
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 12-21
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34223
Human Error Analysis Related to Structural Reliability
Sadao Hattori, Hiroshi Sasakawa, Norihiko Handa
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 22-32
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34224
One-Dimensional Considerations on the Initial Phase of the Chernobyl Accident
Timo A. Vanttola, Markku K. Rajamäki
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 33-74
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34225
Results and Analyses of Dry Rod Consolidation Using Westinghouse Spent-Fuel Assemblies
Krishna Vinjamuri, Edgar M. Feldman, Carlan K. Mullen, Robert C. Hill
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 48-56
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34226
Prediction of Maximum Allowable Temperatures for Dry Storage of Zircaloy-Clad Spent Fuel in Inert Atmosphere
Bryan A. Chin, E. Robert Gilbert
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 57-65
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34227
A Process for Decontaminating Stainless Steels to Release Limits
Aamir Husain
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 66-73
Technical Paper | Chemical Processing | doi.org/10.13182/NT89-A34228
Measurement of the Oxidation of Spent Fuel Between 140 and 225°C
Robert E. Woodley, Robert E. Einziger, H. Craig Buchanan
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 74-88
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34229
SYNROC-FA Waste Form for Immobilization of Amine High-Level Liquid Waste: Process Development and Product Characterization
T. Sampat Sridhar, Ahmad G. Solomah
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 89-97
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34230
A Transient Model for Predicting Nonhomogeneous Nonequilibrium Critical Two-Phase Flows
S. M. Sami, T. Duong
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 98-108
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34231
Fabrication of Curium-Doped SYNROC for an Alpha Radiation Stability Test
Hisayoshi Mitamura, Seiichiro Matsumoto, William J. Buykx, Shingo Tashiro
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 109-117
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT89-A34232
Gamma Transport Theory Analysis of the Three Mile Island Unit 2 Lower Head
Alireza Haghighat, Anthony J. Baratta
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 127-135
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34235
Electron Probe Microanalysis and Scanning Electron Microscopy of Deposits on the Inner Surface of Boiling Water Reactor Cladding
D. N. Sah, C. S. Viswanadham, Sunil Kumar, P. R. Roy
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 136-146
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34236
Reducing Scram Frequency by Relaxing Reactor Trip Setpoints at Maanshan Nuclear Power Station
Ge-Ping Yu, Bau-Shei Pei, Ying-Pang Ma
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 147-159
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34237
Oxidation Behavior of Nonirradiated UO2
Todd K. Campbell, Edgar Robert Gilbert, George D. White, Gregory F. Piepel, Bernard J. Wrona
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 160-171
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34238
CUSEP—A New Mathematical Model of Pulsed Column Contactors Using the Purex Process
John F. Geldard, Adolph L. Beyerlein
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 172-186
Technical Paper | Chemical Processing | doi.org/10.13182/NT89-A34239
An Inference Model for Predicting a Pinching Effect in the Co-Decontamination Extraction Process in a Purex Fuel Reprocessing Plant
Masaki Suwa, Atsuyuki Suzuki
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 187-205
Technical Paper | Chemical Processing | doi.org/10.13182/NT89-A34240
The Behavior of Iodine in a Simulated Spent-Fuel Solution
Tsutomu Sakurai, Akira Takahashi, Niro Ishikawa, Yoshihide Komaki
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 206-212
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34241
A Theoretical Critical Heat Flux Model for Rod Bundles Under Pressurized Water Reactor Conditions
Wen-Shan Lin, Bau-Shei Pei, Chien-Hsiung Lee, I. A. Mudawwar
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 213-226
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34242
Application of Realistic Thermal-Hydraulic Methods for Pressurized Water Reactors with Upper Plenum Injection
Thomas M. Parker, Richard J. Kohrt, Sue I. Dederer, Larry E. Hochreiter, Walter R. Schwarz, Chon-Kwo Tsai, Michael Y. Young
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 227-237
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34243
Comparison of Gamma-Ray Heating Measurements Using Thermoluminescent Dosimeters with Calculations
Khalid A. Al-Hussan, Tien-Ko Wang, Mohamed A. Obeid
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 238-244
Technical Paper | Technique | doi.org/10.13182/NT89-A34244
The Centralized Reliability Data Organization (CREDO) Assessment of Critical Component Unavailability in Liquid-Metal Reactors
Karen H. Koger, M. Jonathan Haire, Brett L. Humphrys, Jay F. Manneschmidt, Keiichi Setoguchi, Ryodai Nakai
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 251-258
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34247
The Development of the Fast-Running Simulation Pressurized Water Reactor Plant Analyzer Code (NUPAC-1)
Kazunori Sasaki, Naotaka Terashita, Takamichi Ogino
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 259-273
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34248
Performance of High-Efficiency Particulate Air Filters Under Severe Conditions
Makoto Osaki, Akira Kanagawa
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 274-284
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34249
Using the RELAP5/MOD2 Code Under Low-Pressure/Low-Temperature Loss-of-Coolant-Accident Conditions
Jan-Li Wang, Jay F. Kunze
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 285-293
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34250
The Performance of the Remote Analytical Laboratory During the First Fluorinel Dissolution Process Campaign
L. C. Lewis, J. P. Henscheid
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 294-299
Technical Paper | Chemical Processing | doi.org/10.13182/NT89-A34251
A Model for the Transient Release of Fission Products from UO2 Fuel: Gasout Code Description
Mukesh Tayal, Lorne D. Macdonald, Erl Kohn, Walter P. Dovigo
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 300-313
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34252
High-Level Liquid Waste Treatment: Process Development Studies in the WIPE Facility—Part I
T. Sampat Sridhar
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 314-323
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34253
Determining the Physical Properties of Steam Generator Tube Scale Using Miniature Specimens
Michael P. Manahan
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 324-333
Technical Paper | Material | doi.org/10.13182/NT89-A34254
Correlation Between Composition Effects on Glass Durability and the Structural Role of the Constituent Oxides
Xiangdong Feng, Ian L. Pegg, Aaron Barkatt, Pedro B. Macedo, Samuel J. Cucinell, Shantao Lai
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 334-345
Technical Paper | Material | doi.org/10.13182/NT89-A34255
A New Non-Fourier Tomographic Filter for Image Reconstruction
R. K. S. Rathore, P. Munshi, P. Arora, S. D. Malik, A. K. Vaish, K. S. Singh, U. Singh
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 346-349
Technical Paper | Technique | doi.org/10.13182/NT89-A34256
