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Fuel Cycle & Waste Management
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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Tomographic Reconstruction of the Density Field Using Radial Polynomials
R. K. S. Rathore, P. Munshi, I. D. Dhariyal, S. T. Swamy
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 7-12
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A34003
Increasing Diesel Start Time for a Boiling Water Reactor (BWR/6) Using the New Emergency Core Cooling System Approach
R. Muralidharan, V. K. Chexal
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 13-23
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A34004
Evacuation Risks: Quantification and Application to Evacuation Scenarios of Nuclear Power Plants
Warren F. Witzig, Sunil D. Weerakkody
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 24-33
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A34005
Organic Iodide Formation During Severe Accidents in Light Water Nuclear Reactors
Edward C. Beahm, Yun-Ming Wang, Simon J. Wisbey, William E. Shockley
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 34-42
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A34006
A Rational Model for the Off-Site Protective Action Selection During Nuclear Reactor Accidents
Sunil D. Weerakkody, Warren F. Witzig
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 43-53
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A34007
Measurements of Capillary Pressure in Urania Debris Beds
Alfred W. Reed, Herbert Meister, Daniel J. Sasmor
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 54-61
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A34008
Application of Carboxylic Acid Cation Exchange Resin to Water Purification in Nuclear Power Plants
Masami Matsuda, Kiyomi Funabashi, Fumio Kawamura, Shunsuke Uchida, Katsumi Ohsumi
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 62-68
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A34009
Direct Dissolution of Nuclear Materials for Chemical Quality Control
Keshav Chander, Bharatkumar N. Patil, Jayshree V. Kamat, Nandakumar B. Khedekar, Remani B. Manolkar, Surendranath G. Marathe
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 69-74
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A34010
Properties of Novel Selective Ion Exchangers for Nuclear Plant Applications
Aaron Barkatt, Karen A. Michael, William Sousanpour, Alisa Barkatt, L. Miguel Penafiel, Pedro B. Macedo, Herbert G. Sutter
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 75-82
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A34011
Development of Materials for Fast Reactor Fuel Assemblies
D. J. Sherwood, A. L. Ward, G. D. Johnson
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 83-89
Technical Paper | Material | doi.org/10.13182/NT87-A34012
A Three-Field Diffusion Model of Three-Phase, Three-Component Flow for the Transient Three-Dimensional Computer Code IVA2/001
Nicolay Ivanov Kolev
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 95-131
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33990
Real-Time Stability Monitoring Method for Boiling Water Reactor Nuclear Power Plants
Kohyu Fukunishi, Satoshi Suzuki
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 132-139
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33991
Analysis of Ex-Core Detector Response Measured During Nuclear Ship Mutsu Land-Loaded Core Critical Experiment
Masafumi Itagaki, Jun-Ichi Abe, Katsuaki Kuribayashi
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 140-150
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33992
Rapid Calculation of Steady-State Concentration Profiles with Nonequilibrium Mass Transfer in Contactors Using the Purex Process
John F. Geldard, Adolph L. Beyerlein, Houn-Lin Chiu
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 151-156
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33993
Experimental Studies of Fission Product Release from Commercial Light Water Reactor Fuel Under Accident Conditions
Morris F. Osborne, Jack L. Collins, Richard A. Lorenz
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 157-169
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A33994
The Impact of Heat Transfer Models on Core/Concrete Interaction
Lainsu Kao, Mujid S. Kazimi
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 170-184
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33995
Stability of Cement-Glass Packages Containing Sodium Borate Salt Generated from Pressurized Water Reactor Power Plants
Tatsuo Izumida, Fumio Kawamura, Koichi Chino, Makoto Kikuchi
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 185-190
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33996
The Recycle Value of Fuel Discharged from Light Water Reactors
Nasir Majid Mirza, Ansar Parvez
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 191-196
Technical Note | Fuel Cycle | doi.org/10.13182/NT87-A33997
A Design Method to Isothermalize the Core of High-Temperature Gas-Cooled Reactors
Makoto Takano, Kazuhiro Sawa
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 207-215
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A15986
Comparison of Heat Transport Capability of a Steam Generator (SG) in a High-Temperature Gas-Cooled Reactor with That of an SG in Other Types of Reactors
Takao Hayashi
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 216-226
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A15987
Preface: Nuclear Power Plant Kalkar (SNR-300)
Wulf Bürkle, Walter H. Köhler
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 229-230
Nuclear Power Plant Kalkar (SNR-300) | doi.org/10.13182/NT87-A15988
Kalkar Nuclear Power Plant (SNR-300)—A Sodium-Cooled Fast Breeder Reactor Prototype
Friedrich H. Morgenstern
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 231-244
Nuclear Power Plant Kalkar (SNR-300) | Fission Reactor | doi.org/10.13182/NT87-A15989
Reactor Vessel System
Helmut Rothfuss, Friedhelm Vogt
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 245-254
Nuclear Power Plant Kalkar (SNR-300) | Fission Reactor | doi.org/10.13182/NT87-A15990
Primary and Secondary Main Piping Systems
Kurt Vinzens, Horst Kappauf
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 255-261
Nuclear Power Plant Kalkar (SNR-300) | Fission Reactor | doi.org/10.13182/NT87-A15991
Fabrication of Intermediate Heat Exchangers, Steam Generators, and Sodium Pumps for SNR-300
Arie Johannes Van ’t Hoft, Jacob Johan de Jong, Jan Piet Vroom, Gerhard Robert Küpers
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 262-277
Nuclear Power Plant Kalkar (SNR-300) | Fission Reactor | doi.org/10.13182/NT87-A15992
Fabrication of Fuel Elements Interplay Between Typical SNR Mark la Specifications and the Fuel Element Fabrication
Willi K. Biermann, Hans-Jochen Heuvel, Servais Pilate, Yvon Vanderborck, Eduard Pelckmans, Guido Vanhellemont, Horst Roepenack, Wolfgang Stoll
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 278-283
Nuclear Power Plant Kalkar (SNR-300) | Fission Reactor | doi.org/10.13182/NT87-A15993
Refueling System Fabrication and Testing
Dieter Althaus, Nicolas Brahy
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 284-294
Nuclear Power Plant Kalkar (SNR-300) | Fission Reactor | doi.org/10.13182/NT87-A15994
Tellurium Behavior in Containment Under Light Water Reactor Accident Conditions
Edward C. Beahm
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 295-302
Nuclear Power Plant Kalkar (SNR-300) | Nuclear Safety | doi.org/10.13182/NT87-A15995
Modeling for Comparison of Leukemia Incidence Risk Between Nuclear and Coal Power Industries
Victor R. Prybutok, Leonard M. Gold
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 303-311
Nuclear Power Plant Kalkar (SNR-300) | Nuclear Safety | doi.org/10.13182/NT87-A15996
Determination of Optimum Alternative Low-Level Radioactive Waste Disposal Site/Disposal Technology Combinations
Marcus H. Voth, Warren F. Witzig
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 312-319
Nuclear Power Plant Kalkar (SNR-300) | Radioactive Waste Management | doi.org/10.13182/NT87-A15997
The EDAC System and New Developments Under Consideration at the Commissariat à I’Energie Atomique for Criticality Accident Detection
Francis Barbry, Raymond Prigent
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 320-325
Nuclear Power Plant Kalkar (SNR-300) | Criticality Safety | doi.org/10.13182/NT87-A15998
