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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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 Dynamic Model for Predicting CANDU Pressurizer Performance
Samir M. Sami
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 7-23
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33747
Some Transient Characteristics of PIUS
Yoshiro Asahi, Hiroaki Wakabayashi
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 24-33
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33748
Analytical Simulation of Boiling Water Reactor Pressure Suppression Pool Swell
Stanley K. Widener
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 34-38
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33749
Iodine-131 Species in the Stack Exhaust Air of Light Water Reactors
H. Deuber
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 39-43
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33750
Investigations on the Retention of Elemental Radioiodine by Activated Carbons at High Temperatures
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 44-48
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33751
Interpretation of Conductivity-Sensitive Liquid-Level Transducer Signals in a Small Break Loss-of-Coolant Accident Test Facility
Yassin A. Hassan
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 49-58
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33752
Development and Fabrication of 70% PuC—30% UC Fuel for the Fast Breeder Test Reactor in India
Chaitanyamoy Ganguly, Parameshwar Venkappa Hegde, Gyan Chand Jain, Uddharan Basak, Radhey Shyam Mehrotra, Sukomal Majumdar, Pradip Ranjan Roy
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 59-69
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A33753
A New Gaseous Gap Conductance Relationship
David A. Wesley, M. Michael Yovanovich
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 70-74
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A33754
A Bounding Assessment Method for Correlating Measured Gas Leaks to the Possible Loss of Particulate Contents from Radioactive Materials Packages
John A. Andersen
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 75-83
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33755
Volatilization of Cesium from Nuclear Waste Glass in a Canister
Hiroshi Kamizono, Shizuo Kikkawa, Shingo Tashiro, Haruto Nakamura
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 84-88
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33756
Disposal of High-Level Radioactive Waste in Argillaceous Formations: In Situ and Laboratory Heating Experiments
Emilio Tassoni, Ferruccio Gera
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 89-98
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33757
Derivative Method for Edge Enhancement in Radiographic Testing
Dov Ingman, Amos Notea
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 99-104
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT86-A33758
On the Friction Factor for Fully Developed Turbulent Sodium Flow in Small Smooth Tubes
Naozo Hattori, Kenji Hayashi
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 105-116
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT86-A33759
A Process Inherent Ultimate Safety Boiling Water Reactor
Charles W. Forsberg
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 121-134
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33735
Modeling of Boron Control During Power Transients in a Pressurized Water Reactor
Philippe Mathieu, E. Distexhe
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 135-147
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33736
Modeling of Multiple-Component Aerosols — Sensitivities to Assumptions
Hans Jordan, Philip M. Schumacher, Vladimir Kogan
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 148-157
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33737
Source Term Characterization for the Maxey Flats Low-Level Radioactive Waste Disposal Site
Ramesh Dayal, Richard F. Pietrzak, James H. Clinton
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 158-177
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33738
A Melt Refining Method for Uranium-Contaminated Aluminum
Tatsuhiko Uda, Hajime Iba, Kiyoshi Hanawa
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 178-183
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33739
Oxidation-Induced Geochemical Changes in Trench Leachates from the Maxey Flats Low-Level Radioactive Waste Disposal Site
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 184-193
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33740
Stationary Transport of Dissolved Species in the Backfill Surrounding a Waste Canister in Fissured Rock: Some Simple Analytical Solutions
Ivars Neretnieks
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 194-200
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33741
Track-Etch Neutron Radiography with a New Boron Carbide Converter
Genichi Matsumoto, Naohide Murata, Soju Suzuki, Mitsugu Matsumoto, Kohei Ohkubo, Yasushi Ikeda
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 201-211
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT86-A33742
Design of a New Counting Cell for Monitoring 85Kr in Environmental Air Samples
Jiunn-Guang Lo, Dar-Yeong Chen, Jen-Zen Wang
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 212-217
Technical Paper | Technique | doi.org/10.13182/NT86-A33743
Nonproliferation Issue of the Pebble Bed High-Temperature Reactor
E. Teuchert, K. A. Haas
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 218-222
Technical Note | Fission Reactor | doi.org/10.13182/NT86-A33744
Occupational Dose Reduction Experience in Ontario Hydro Nuclear Power Stations
R. Wilson, G. A. Vivian, W. J. Chase, G. Armitage, L. J. Sennema
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 231-245
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Safety | doi.org/10.13182/NT86-A33762
Radiation Protection Practices and Experience in French Operating Reactors
André Gauvenet
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 246-253
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Safety | doi.org/10.13182/NT86-A33763
Health Physics Practices and Experience at Duke Power Company
Lionel Lewis
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 254-257
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Safety | doi.org/10.13182/NT86-A33764
Fission Product Behavior in High-Burnup Water Reactor Fuel Subjected to Slow Power Increases
Per Knudsen, Carsten Bagger, Hans Carlsen, Ib Misfeldt, Mogens Mogensen
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 258-267
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor | doi.org/10.13182/NT86-A33765
The Reactor Containment of Standard-Design German Pressurized Water Reactors
Wolfgang K. E. Braun, Klaus Hassmann, Hans-Henning Hennies, J. Peter Hosemann
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 268-290
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor | doi.org/10.13182/NT86-A33766
Effective Use of Sensor Readings in On-Line Plant Monitoring and Its Application to Boiling Water Reactor Power Distribution Calculations
Takaharu Fukuzaki, Takashi Kiguchi
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 291-300
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor | doi.org/10.13182/NT86-A33767
A Dynamic Model for Pressurized Water Reactor Analysis on Microcomputers
Parveen K. Jain
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 301-311
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor | doi.org/10.13182/NT86-A33768
Alternative Fuel Cycle Evaluation in the Federal Republic of Germany
Reiner Papp, Klaus-Detlef Closs
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 312-320
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fuel Cycle | doi.org/10.13182/NT86-A33769
Fuel-Number Recognition by Means of Multidirectional Lighting
Makoto Senoh, Sakae Sugiyama, Masayoshi Sasaki
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 321-327
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Fuel | doi.org/10.13182/NT86-A33770
Model for Fuel/Cladding Chemical Interaction
Kenji Konashi, Katsuichiro Kamimura, Yoji Yokouchi
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 328-337
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Fuel | doi.org/10.13182/NT86-A33771
Microscopic Investigation into the Irradiation Behavior of U3O8-Al Dispersion Fuel
Gerard L. Hofman, George L. Copeland, John E. Sanecki
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 338-344
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Fuel | doi.org/10.13182/NT86-A33772
The Use of Reconstituted Charpy Specimens to Extend R. E. Ginna Reactor Pressure Surveillance Data
Regis P. Shogan, Stephen E. Yanichko, William S. Galloway
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 345-352
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Material | doi.org/10.13182/NT86-A33773
A 2D(γ,n)1H Tritiated Water Detector with 232U/228Th Source
Norman P. Baumann, Willard G. Winn
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 353-358
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Analyse | doi.org/10.13182/NT86-A33774
Spatial Variability of the Distribution Coefficients of 137Cs, 65Zn, 85Sr, 57Co, 109Cd, 141Ce, 103Ru, 95mTc, and 131l in a Cultivated Soil
Heinz Bachhuber, Kurt Bunzl, Wolfgang Schimmack
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 359-371
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Analyse | doi.org/10.13182/NT86-A33775
Movement of Droplets in the Centrifugal Settler
Hiromichi Fumoto, Riyohei Kiyose
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 372-374
Technical Note | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Chemical Processing | doi.org/10.13182/NT86-A33776
