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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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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RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
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Nuclear Design and Economic Comparison of a Conventional and Bullseye Liquid-Metal Fast Breeder Reactor Core
J. A. Vitti, L. D. Felten, N. G. Galluzzo, J. M. Otter, J. C. Brittingham
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 10-20
Technical Paper | Reactor | doi.org/10.13182/NT79-A32235
Physics Studies of a Heterogeneous Liquid-Metal Fast Breeder Reactor
Michael J. Lineberry, Harold F. McFarlane, Peter J. Collins, Stuart G. Carpenter
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 21-43
Technical Paper | Reactor | doi.org/10.13182/NT79-A32236
Performance Characteristics of Homogeneous Versus Heterogeneous Liquid-Metal Fast Breeder Reactors
W. P. Barthold, J. C. Beitel
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 44-60
Technical Paper | Reactor | doi.org/10.13182/NT79-A32237
Physics Performances of a Heterogeneous Fast Reactor Core Concept Studied in MASURCA
Y. H. Bouget, M. Cosimi, P. Hammer, G. Humbert, F. Lyon, M. Martini
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 61-75
Technical Paper | Reactor | doi.org/10.13182/NT79-A32238
Nuclear Performance of Liquid-Metal Fast Breeder Reactors Designed to Preclude Energetic Hypothetical Core Disruptive Accidents
H. S. Bailey, Y. S. Lu
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 76-82
Technical Paper | Reactor | doi.org/10.13182/NT79-A32239
Preface: Occupational Radiation Exposure at Nuclear Power Plants
E. A. Warman
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Page 83
Occupational Radiation Exposure at Nuclear Power Plants | doi.org/10.13182/NT79-A32240
Occupational Radiation Exposure at French Power Plants: Measurement and Prediction
P. Beslu, G. Frejaville, P. Jeanson
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 84-90
Technical Paper | Reactor | doi.org/10.13182/NT79-A32241
Quantifying Plant Availability, ALARA, and Occupational Radiation Exposure Relationships
Philip M. Garrett
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 91-96
Technical Paper | Reactor | doi.org/10.13182/NT79-A32242
Getting at the Source: Reducing Radiation Fields
Robert A. Shaw
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 97-103
Technical Paper | Reactor | doi.org/10.13182/NT79-A32243
Development of a Diagnosis System for a Boiling Water Reactor
Fumio Murata, Kanji Kato, Fumio Tomizawa, Isao Sumida
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 104-117
Technical Paper | Reactor | doi.org/10.13182/NT79-A32244
Analysis of the Interaction of Fuel Channels with the End Shields in CANDU Reactors
S. R. MacEwen, A. R. Causey
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 118-131
Technical Paper | Reactor | doi.org/10.13182/NT79-A32245
Mitigating Community Impacts of Energy Development: Some Examples for Coal and Nuclear Generating Plants in the U.S.
Elizabeth Peelle
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 132-140
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32246
Critical Experiments with Fast Test Reactor Fuel Pins in Water
S. R. Bierman, B. M. Durst, E. D. Clayton, R. I. Scherpelz, Howard T. Kerr
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 141-151
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A32247
Economic Performance of Liquid-Metal Fast Breeder Reactor and Gas-Cooled Fast Reactor Radial Blankets
Nicholas Tsoulfanidis, M. Hossein Jankhah*
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 152-171
Technical Paper | Economic | doi.org/10.13182/NT79-A32248
Multiaxial Creep Equations for Nonlinear and Volume-Nonconservative In-Reactor Creep
M. M. Hall, Jr.
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 172-176
Technical Paper | Material | doi.org/10.13182/NT79-A32249
Study of an Optimum Design for Subcritical Neutron Multipliers Using Californium-252 Neutron Sources
B. Wei-Teh Lee, S. H. Levine, W. A. Jester
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 177-187
Technical Paper | Radioisotope | doi.org/10.13182/NT79-A32250
Application of the Self-Powered Detector Concept in the Design of a Threshold Gamma-Ray Detector
F. E. LeVert
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 188-191
Technical Paper | Instrument | doi.org/10.13182/NT79-A32251
Plutonium Isotopic Calculations for a Modern Light Water Reactor
R. D. Mosteller*, Warren M. Andrews, Odelli Ozer, W. J. Eich
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 192-197
Technical Note | Fuel Cycle | doi.org/10.13182/NT79-A32252
Transverse Flow in High-Temperature Gas-Cooled Reactor Graphite Elements
Karol J. Mysels
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 203-209
Technical Paper | Reactor | doi.org/10.13182/NT79-A32255
Experimental Study of Scram Transients in Generalized Liquid-Metal Fast Breeder Reactor Outlet Plenums
Paul A. Howard, Juan J. Carbajo
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 210-220
Technical Paper | Reactor | doi.org/10.13182/NT79-A32256
An Improved Water Density Feedback Model for Pressurized Water Reactors
A. L. Casadei, P. J. Turinsky
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 221-230
Technical Paper | Reactor | doi.org/10.13182/NT79-A32257
On the Use of a Bayesian Reasoning in Safety and Reliability Decisions—Three Examples
Stan Kaplan, B. John Garrick
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 231-245
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32258
EFLOD Code for Reflood Heat Transfer
Rodney R. Gay
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 246-257
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32259
An Automated Procedure for Selection of Optimal Refueling Policies for Light Water Reactors
Bo-In Lin, Burt Zolotar, Joel Weisman
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 258-275
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A32260
Factors Affecting Defective Fraction of Biso-Coated High-Temperature Gas-Cooled Reactor Fuel Particles During In-Block Carbonization
A. J. Caputo, D. R. Johnson, C. K. Bayne
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 276-283
Technical Paper | Fuel | doi.org/10.13182/NT79-A32261
Migratory Properties of Some Nuclear Waste Elements in Geologic Media
M. G. Seitz, P. G. Rickert, S. Fried, A. M. Friedman, M. J. Steindler
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 284-296
Technical Paper | Radioactive Waste | doi.org/10.13182/NT79-A32262
Control of Stress Corrosion Cracking in Storage Tanks Containing Radioactive Waste
R. S. Ondrejcin, S. P. Rideout, J. A. Donovan
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 297-306
Technical Paper | Material | doi.org/10.13182/NT79-A32263
Separative Performance Transients in a Gas Centrifuge
D. R. Olander
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 307-314
Technical Paper | Isotope Separation | doi.org/10.13182/NT79-A32264
D-D Neutron and X-Ray Yields from High-Power Deuterium Beam Injectors
Jinchoon Kim
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 315-321
Technical Paper | Accelerator | doi.org/10.13182/NT79-A32265
The Effect of Liquid-Metal Protection Schemes in Inertial Confinement Fusion Reactors
Halil I. Avci, Gerald L. Kulcinski
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 333-345
Technical Paper | Reactor | doi.org/10.13182/NT79-A32270
Convective Helium Cooling of Grids in Continuously Operated Neutral Beam Injectors
M. A. Hoffman
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 346-356
Technical Paper | Reactor | doi.org/10.13182/NT79-A32271
Accident Progression for a Loss-of-Heat-Sink with Scram in a Liquid-Metal Fast Breeder Reactor
R. A. Bari, H. Ludewig, W. T. Pratt, Y. H. Sun
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 357-380
Technical Paper | Reactor | doi.org/10.13182/NT79-A32272
Performance Parameters for Fusion-Fission Power Systems
D. J. Bender
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 381-389
Technical Paper | Reactor | doi.org/10.13182/NT79-A32273
Effect of Fluid-to-Structure Heat Transfer on the Structural Damage Potential to a Liquid-Metal Fast Breeder Reactor
S. J. Hakim, P. B. Abramson
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 390-400
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32274
An Evaluation of the Thermal-Hydraulic and Fuel Rod Thermal and Mechanical Deformation Behavior During the First Power Burst Facility Nuclear Blowdown Tests
Philip E. MacDonald, James M. Broughton, Jay W. Spore
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 401-410
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32275
The Physical State of Post-Loss-of-Coolant Accident Containment Atmospheres
Kazys K. Almenas, Joseph M. Marchello
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 411-428
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32276
Optimal Linear Combinations of Accounting Data for the Detection of Nonconstant Losses
Hans H. Frick
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 429-432
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A32277
Fabrication of Grid-Spaced Bundle for the F-5 (X317) Irradiation Experiment
J. R. Lindgren, P. W. Flynn, L. C. Foster
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 433-444
Technical Paper | Fuel | doi.org/10.13182/NT79-A32278
ELESIM: A Computer Code for Predicting the Performance of Nuclear Fuel Elements
M. J. F. Notley
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 445-450
Technical Paper | Fuel | doi.org/10.13182/NT79-A32279
