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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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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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Boiling Water Reactor Control Rod Programming Using Heuristic and Mathematical Methods
Tamotsu Hayase, Hiroshi Motoda
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 91-100
Technical Paper | Reactor | doi.org/10.13182/NT80-A32455
A Radionuclide Trap for Liquid-Metal-Cooled Reactors
J. C. McGuire, W. F. Brehm
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 101-109
Technical Paper | Reactor | doi.org/10.13182/NT80-A32456
Reaction Rate Calculations in Uranium and Thorium Blankets Surrounding a Central Deuterium-Tritium Neutron Source
A. D. Krumbein, M. Lemanska, M. Segev, J. J. Wagschal, A. Yaari
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 110-116
Technical Paper | Reactor | doi.org/10.13182/NT80-A32457
Rotating Plug Size Study for Liquid-Metal Fast Breeder Reactors
L. J. Nemeth
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 117-121
Technical Paper | Reactor | doi.org/10.13182/NT80-A32458
Experimental Value of Percent Variation in Root-Mean-Square Ex-Core Detector Signal to the Core Barrel Amplitude Scale Factor
J. P. Thompson, G. R. McCoy, B. T. Lubin
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 122-127
Technical Paper | Reactor | doi.org/10.13182/NT80-A32459
Critical Experiments with Solid Neutron Absorbers and Water-Moderated Fast Test Reactor Fuel Pins
B. M. Durst, S. R. Bierman, E. D. Clayton, J. F. Mincey
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 128-149
Technical Paper | Fuel | doi.org/10.13182/NT80-A32460
Remodeling and Dosimetry on the Neutron Irradiation Facility of the Musashi Institute of Technology Reactor for Boron Neutron Capture Therapy
Otohiko Aizawa, Keiji Kanda, Tetsuya Nozaki, Tetsuo Matsumoto
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 150-163
Technical Paper | Radiation | doi.org/10.13182/NT80-A32461
Subcritical Limits for Special Fissile Actinides
H. K. Clark
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 164-170
Technical Paper | Analysis | doi.org/10.13182/NT80-A32462
Effects of Indoor Residence on Radiation Doses from Routine Releases of Radionuclides to the Atmosphere
D. C. Kocher
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 171-179
Technical Note | Radioisotope | doi.org/10.13182/NT80-A32463
An Experimental Technique for Determination of Steam Fraction in Flowing Steam / Air Mixtures
N. Saba, R. T. Lahey, Jr., J. C. Corelli
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 5-15
Technical Paper | Reactor | doi.org/10.13182/NT80-A32443
Pellet and Pellet-Blanket Neutronics and Photonics for Electron Beam Fusion
Magdi M. H. Ragheb, Gregory A. Moses, Charles W. Maynard
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 16-33
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32444
Multigoal Fuel Cycle Optimization Including Nonproliferation Objectives
P. Silvennoinen, T. Vieno, J. Vira
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 34-42
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32445
Fission Gas Release and Microscopic Swelling in Highly Rated Advanced Fuels
M. Coquerelle, C. T. Walker
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 43-53
Technical Paper | Fuel | doi.org/10.13182/NT80-A32446
Reprocessing Nuclear Fuels of the Future: A Radiological Assessment of Advanced (Th,U) Carbide Fuel
J. E. Till, H. R. Meyer, L. E. Morse, W. D. Bond, E. S. Bomar, V. J. Tennery
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 54-62
Technical Paper | Fuel | doi.org/10.13182/NT80-A32447
Analysis, Critique, and Reevaluation of High-Level Waste Repository Water Intrusion Scenario Studies
Bernard L. Cohen
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 63-69
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32448
Effects of Simulated Fission Products on the Mechanical Properties of Zircaloy-2
R. Kohli, F. Holub
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 70-76
Technical Paper | Material | doi.org/10.13182/NT80-A32449
Desorption Kinetics of Methyl Iodide from Impregnated Charcoal
Leonard A. Jonas, Victor R. Deitz, J. B. Romans
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 77-83
Technical Paper | Radioisotope | doi.org/10.13182/NT80-A32450
Dose Rates from Induced Activity in the Tokamak Fusion Test Reactor Test Cell
R. G. Alsmiller, Jr., J. Barish, R. T. Santoro, R. A. Lillie, J. M. Barnes, M. M. H. Ragheb
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 187-195
Technical Paper | Reactor | doi.org/10.13182/NT80-A32466
Impurity Deposition in a Mesh-Packed Cold Trap
Michio Murase, Isao Sumida, Norio Nagase, Kazuo Mukai, Osamu Onuki
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 196-203
Technical Paper | Reactor | doi.org/10.13182/NT80-A32467
Development Studies Regarding the Construction of Epithermal-Enriched Neutron Field for Medical Purposes at the University of Tokyo YAYOI Fast Reactor
Shigehiro An, Akira Furuhashi, Yoshiaki Oka, Masatsugu Akiyama, Hiroyuki Kuga,+, Harukuni Tanaka
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 204-215
Technical Paper | Reactor | doi.org/10.13182/NT80-A32468
Nuclear Performance of Molten Salt Fusion-Fission Symbiotic Systems for Catalyzed Deuterium-Deuterium and Deuterium-Tritium Reactors
M. M. H. Ragheb, R. T. Santoro, J. M. Barnes, M. J. Saltmarsh
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 216-232
Technical Paper | Reactor | doi.org/10.13182/NT80-A32469
On the Volatilization Potential of Metallic Inclusions Found in Irradiated UO2 Fuel During Overheating Events
Paul Sasa, August W. Cronenberg+, Michael G. Stevenson
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 233-250
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32470
Supercriticality Through Optimum Moderation in Nuclear Fuel Storage
J. M. Cano, R. Caro, J. M. Martnez-Val
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 251-260
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32471
International Symbiosis: The Role of Thorium and The Breeders
D. M. Ligon, R. H. Brogli
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 261-272
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32472
Development and Performance of Metal Fuel Elements for Fast Breeder Reactors
L. C. Walters, J. H. Kittel
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 273-280
Technical Paper | Fuel | doi.org/10.13182/NT80-A32473
The Effect of Low Pressurized Water Reactor Containment Pressure on Peak Cladding Temperatures
Vincent P. Manno
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 281-288
Technical Paper | Fuel | doi.org/10.13182/NT80-A32474
Application of Simplified Reliability Methods for Risk Assessment of Nuclear Waste Repositories
Andreas Pritzker, Jrg Gassmann
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 289-297
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32475
Corrosion of 15 Cr—35 Ni—50 Fe Doped with Niobium, Titanium, or Molybdenum in High Temperature Reactor Helium
Otto Demel
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 298-302
Technical Paper | Material | doi.org/10.13182/NT80-A32476
Empirical Development of Irradiation-Induced Swelling Design Equations
J. F. Bates, M. K. Korenko
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 303-314
Technical Paper | Material | doi.org/10.13182/NT80-A32477
