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Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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Core Motion Monitoring
Joseph A. Thie
Nuclear Technology | Volume 45 | Number 1 | August 1979 | Pages 5-45
Critical Review | doi.org/10.13182/NT79-A32283
A Neutronic Analysis of Boiling Water Reactor In-Core Detector Noise
Hsiang-Shou Cheng, David J. Diamond
Nuclear Technology | Volume 45 | Number 1 | August 1979 | Pages 46-53
Technical Paper | Reactor | doi.org/10.13182/NT79-A32284
Mass-Energy Analyses for Gas-Cooled Fast Reactor and Fusion-Fission Hybrid Reactor Systems
Michael R. Jonzen
Nuclear Technology | Volume 45 | Number 1 | August 1979 | Pages 54-67
Technical Paper | Reactor | doi.org/10.13182/NT79-A32285
Application of Drift Flux to Transient Two-Phase Level Swell
Leonard W. Ward
Nuclear Technology | Volume 45 | Number 1 | August 1979 | Pages 68-76
Technical Paper | Reactor | doi.org/10.13182/NT79-A32286
Nucleonic Design for a Compact Tokamak Fusion Reactor Blanket and Shield
E. T. Cheng, C. W. Maynard, W. F. Vogelsang, A. C. Klein
Nuclear Technology | Volume 45 | Number 1 | August 1979 | Pages 77-98
Technical Paper | Reactor | doi.org/10.13182/NT79-A32287
Uncertainties in Radiological Assessments—A Statistical Analysis of Radioiodine Transport via the Pasture-Cow-Milk Pathway
D. Lynn Shaeffer, F. Owen Hoffman
Nuclear Technology | Volume 45 | Number 1 | August 1979 | Pages 99-106
Technical Paper | Radioactive Waste | doi.org/10.13182/NT79-A32288
Neutronic Performance of Fusion Reactor Blankets with Different Coolants and Structural Arrangements
J. Chao, B. B. Miki, N. E. Todreas
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 113-120
Technical Paper | Reactor | doi.org/10.13182/NT79-A32302
Performance Test of the Upper Head Injection System at the ROSA-II Test Facility
K. Tasaka, H. Adachi, M. Sobajima, K. Soda, M. Suzuki, M. Okazaki, M. Shiba
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 121-139
Technical Paper | Reactor | doi.org/10.13182/NT79-A32303
Lattice Calculations and Three-Dimensional Effects in a Laser Fusion-Fission Reactor
Magdi M. H. Ragheb, Said I. Abdel-Khalik, Mahmoud Youssef, Charles W. Maynard
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 140-152
Technical Paper | Reactor | doi.org/10.13182/NT79-A32304
Highly Compacted Sodium Bentonite for Isolating Rock-Deposited Radioactive Waste Products
Roland Pusch
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 153-157
Technical Paper | Radioactive Waste | doi.org/10.13182/NT79-A32305
Measurements of Hydrogen Concentration in Liquid Sodium by Using an Inert Gas Carrier Method
Toshio Funada, Isao Nihei, Shunichi Yuhara, Takashi Nakasuji
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 158-165
Technical Paper | Material | doi.org/10.13182/NT79-A32306
Experimental Investigation of Various Pellet Geometries to Reduce Strains in Zirconium Alloy Cladding
T. J. Carter
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 166-176
Technical Paper | Material | doi.org/10.13182/NT79-A32307
Neutron Gauge for Measurement of High Void Fraction in Water-Steam Mixtures
Franco Vittorio Frazzoli, Alberto Magrini
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 177-182
Technical Paper | Instrument | doi.org/10.13182/NT79-A32308
Tritium Levels in Urine of Occupationally Exposed Persons Caused by Different Types of Working Conditions
K. Irlweck, H. Sorantin
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 183-187
Technical Paper | Radiation | doi.org/10.13182/NT79-A32309
Thermal Analysis of Ammonium Diuranate
C. N. Turcanu, R. Deju
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 188-192
Technical Paper | Analysis | doi.org/10.13182/NT79-A32310
Thermal-Neutron Flux Depression in Cylindrical UO2 Fuel Rods
James E. Gibson, J. N. Anno
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 193-194
Technical Note | Fuel | doi.org/10.13182/NT79-A32311
Concentric-Sphere Design for Spacing of Tag-Gas Isotopic Ratios
Kenny C. Gross
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 195-197
Technical Note | Fuel | doi.org/10.13182/NT79-A32312
Analytic Prediction of Thermal Profile Development and Inversion for Use in In-Pile Experimentation
David P. Weber
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 203-218
Technical Paper | Reactor | doi.org/10.13182/NT79-A32291
Decay Spectra of Fission Products from Uranium-235 Thermal Fission: Comparison of Calculations with Experiments
M. G. Stamatelatos, T. R. England
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 219-232
Technical Paper | Reactor | doi.org/10.13182/NT79-A32292
Compatibility Consideration for Zero Moment Tokamak Toroidal Field Coils
S. L. Gralnick, I. U. Ojalvo, I. J. Zatz, T. Balderes
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 233-243
Technical Paper | Reactor | doi.org/10.13182/NT79-A32293
Dynamic Analysis of a Fusion System Using the System Transfer Function
S. Bian
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 244-248
Technical Paper | Reactor | doi.org/10.13182/NT79-A32294
TREAT Test H6—A 50 cent/s Transient Overpower Accident Simulation
Richard J. Page, Charles L. Fink, Alan B. Rothman, Robert K. Lo, Lewis E. Robinson, Paul H. Froehle
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 249-268
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32295
Technical Consideration of the Use of Nuclear Fuel Spikants for Proliferation Deterrence
J. E. Selle, P. Angelini, R. H. Rainey, J. I. Federer, A. R. Olsen
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 269-286
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A32296
The External Gelation of Thorium Process for Preparation of ThO2 and (Th,U)O2 Fuel Kernels
H. D. Ringel, E. Zimmer
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 287-298
Technical Paper | Fuel | doi.org/10.13182/NT79-A32297
Power Production and Actinide Elimination by Fast Reactor Recycle
D. J. Murphy, Jr., W. M. Farr, B. D. Ganapol
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 299-306
Technical Paper | Radioactive Waste | doi.org/10.13182/NT79-A32298
