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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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 New Approach to Simplified Liquid-Metal Fast Breeder Reactor Plant Design
Morihiko Sato, Norihiko Handa
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 7-12
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34331
Probabilistic Risk Assessment Based Guidance for Piping In-Service Inspection
Truong V. Vo, Bryan F. Gore, Elizabeth J. Eschbach, Fredric A. Simonen
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 13-20
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34332
Passive Safety Testing at the Fast Flux Test Facility
D. M. Lucoff
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 21-29
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34333
Melt Propagation in Dry Core Debris Beds
Sudip S. Dosanjh
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 30-46
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34334
Reduction Stripping of Low-Concentration Np(VI) Loaded on 30% Tri-n-Butyl Phosphate Through Laser-Induced Reactions
Youichi Enokida, Atsuyuki Suzuki
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 47-54
Technical Paper | Chemical Processing | doi.org/10.13182/NT89-A34335
Retardation Factor of a Radionuclide for Undisturbed and Disturbed Sandy Soil
Toshihiko Ohnuki, Tadao Tanaka, Hiromichi Ogawa, Tadatoshi Yamamoto
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 55-63
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34336
Dryout Heat Fluxes for Surfaces Overlayed with Chimney-Type Porous Deposits
Chin Pan, Barclay G. Jones, Albert J. Machiels
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 64-74
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34337
Thermohydraulic Investigations of Decay Heat Removal Systems by Natural Convection for Liquid-Metal Fast Breeder Reactors
Helmut Hoffmann, Dietrich Weinberg, Yoshiaki Ieda, Klaus Marten, Herbert Tschöke, Hans-Heinz Frey, Kurt Dres
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 75-86
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34338
Development of a Three-Dimensional Transient Code for Reactivity-Initiated Events in Boiling Water Reactors— Models and Code Verifications
Hitoshi Uematsu, Sadayuki Izutsu, Toru Yamamoto, Ryutaro Yamashita, Sakae Muto, Akio Toba
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 87-97
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34339
Executive Summary: Research in Nuclear Power—Workshop on the Needs of the Next Generation of Nuclear Power Technology
A. David Rossin, Kunmo Chung, K. L. Peddicord
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 107-119
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor | doi.org/10.13182/NT89-A34318
Nuclear Power Technology: A Mandate for Change
Kunmo Chung, George A. Hazelrigg
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 120-128
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor | doi.org/10.13182/NT89-A34319
The Integral Fast Reactor
Yoon I. Chang
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 129-138
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor | doi.org/10.13182/NT88-129
Modularized High-Temperature Gas-Cooled Reactor Systems
David D. Lanning
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 139-156
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor | doi.org/10.13182/NT89-A34321
Opportunities for Automation and Control of the Next Generation of Nuclear Power Plants
Robert E. Uhrig
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 157-165
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor | doi.org/10.13182/NT89-A34322
A Look at Safety Goals and Safety Design Trends for Advanced Light Water Power Reactors
David Okrent
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 166-169
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Nuclear Safety | doi.org/10.13182/NT89-A34323
Materials Research Needs for Near-Term Nuclear Reactors
John R. Weeks
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 170-174
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Material | doi.org/10.13182/NT89-A34324
The European Breeder Program
G. Cicognani, A. M. Broomfield, R. Lallement, W. Marth
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 175-182
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor | doi.org/10.13182/NT89-A34325
Fast Breeder Reactors for Energy Security
William M. Jacobi
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 183-189
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor | doi.org/10.13182/NT89-A34326
A Versatile Facility at Windscale, United Kingdom, for the Fabrication of Experimental Mixed Uranium-Plutonium-Oxide Nuclear Fuel
Hugh M. MacLeod, George R. Chilton, J. Alan Dodd
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 190-200
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fuel Cycle | doi.org/10.13182/NT89-A34327
A New Mixed Fossil/Nuclear Energy System for the Production of Electricity with Zero Emission of Carbon Dioxide
W. Seifritz
Nuclear Technology | Volume 88 | Number 2 | November 1989 | Pages 201-206
Technical Paper | NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Economic | doi.org/10.13182/NT89-A34328
Release of Radioactive Materials in Simulation Tests of a Postulated Solvent Fire in a Nuclear Fuel Reprocessing Plant
Gunji Nishio, Kazuichiro Hashimoto
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 213-226
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34305
Analysis of a Main Steam Isolation Valve Closure Anticipated Transient Without Scram in a Boiling Water Reactor
T. J. Liaw, Chin Pan, Gen-Shun Chen, Jung-Kue Hsiue
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 227-238
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34306
Depressurization to Mitigate Direct Containment Heating
Rosanna Chambers, Duane J. Hanson, R. Jack Dallman, Fuat Odar
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 239-250
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34307
Heuristic Optimization of Pressurized Water Reactor Fuel Cycle Design Under General Constraints
Hoju Moon, Samuel H. Levine, Moussa Mahgerefteh
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 251-261
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34308
Design Study for an Advanced Liquid-Metal Fast Breeder Reactor Core with High Burnup
Tatsutoshi Inagaki, Hiroyuki Kuga, Masao Suzuki, Tsugio Yokoyama, Mitsuaki Yamaoka, Kunikazu Kaneto, Masahisa Ohashi, Kunitoshi Kurihara
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 262-282
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34309
The Fast Breeder Reactor Fuel Cycle in Europe—Present Status and Prospects
Jean Mégy, Robert Harold Allardice, Klaus Ebert, Jean-Marie Morelle, Paolo Venditti
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 283-289
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34310
Dissolution of PuO2 in Hydrochloric Acid Medium—Effect of Reducing Agents
Mrs. Shakila Abdul Majeed, Thandangorai Ganapathi Srinivasan, Kanwal Nain Sabharwal
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 290-293
Technical Paper | Chemical Processing | doi.org/10.13182/NT89-A34311
An Improved Theoretical Critical Heat Flux Model for Low-Quality Flow
Wen-Shan Lin, Chien-Hsiung Lee, Bau-Shei Pei
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 294-306
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34312
Moderator Circulation in CANDU Reactors: An Alternative Approach for the Tube Matrix Simulation
Hassan E. S. Fath, Makarem A. Hussein
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 307-318
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34313
A Null-Type Boronimeter for On-Line Analysis
Carol A. Jaeger, Eric R. Ellis, Thomas F. Parkinson
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 319-324
Technical Paper | Technique | doi.org/10.13182/NT89-A34314
Calibrating a Vacuum Ionization Gauge for Hydrogen Using a Frit-Type Plugging Meter
DeeEarl Vaden
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 325-331
Technical Paper | Technique | doi.org/10.13182/NT89-A34315
