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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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Irradiation Behavior of Experimental Mark-II Experimental Breeder Reactor II Driver Fuel
G. L. Hofman
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 7-22
Technical Paper | Reactor | doi.org/10.13182/NT80-A32408
Effect of Intrasubassembly Incoherencies on the Fast Test Reactor Unprotected Transient Overpower Accident
Shu-Chien Yung, Norman P. Wilburn
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 23-38
Technical Paper | Reactor | doi.org/10.13182/NT80-A32409
Analysis of the Differences in Breeding Ratio and Fissile Inventory Between Heterogeneous and Homogeneous Liquid-Metal Fast Breeder Reactors
Constantine P. Tzanos
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 39-50
Technical Paper | Reactor | doi.org/10.13182/NT80-A32410
Criticality Experiments with Subcritical Clusters of Low Enriched UO2 Rods in Water with Uranium or Lead Reflecting Walls
S. R. Bierman, B. M. Durst, E. D. Clayton
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 51-58
Technical Paper | Reactor | doi.org/10.13182/NT80-A32411
Development of a Dynamics Model for the Research Reactor Maria
Jerzy Kubowski
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 59-69
Technical Paper | Reactor | doi.org/10.13182/NT80-A32412
Gravitational Collision Efficiency of Post Hypothetical Core Disruptive Accident Liquid-Metal Fast Breeder Reactor Aerosols: Spherical Particles
G. A. Pertmer, S. K. Loyalka
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 70-90
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32413
The Role of Fission Gas and Fuel Melting in Fuel Response During Simulated Hypothetical Loss-of-Flow Transients
G. Bandyopadhyay, J. A. Buzzell
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 91-109
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32414
Design Against Weathering of Iodine Filters
Yakov Ben-Haim
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 110-118
Technical Paper | Chemical Processing | doi.org/10.13182/NT80-A32415
Helium Fill Gas Absorption in Pressurized UO2 Fuel Rods During Irradiation
K. Vinjamuri, D. E. Owen
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 119-124
Technical Paper | Fuel | doi.org/10.13182/NT80-A32416
Heat Transfer in Pressurized Water Reactor Components Most Often Subject to Thermal Shock
F. Parras, M. Bosser, D. Milan, G. Berthollon
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 125-152
Technical Paper | Fuel | doi.org/10.13182/NT80-A32417
Design of High-Performance Fuel Pin Simulators for Thermodynamic Experiments with Nuclear Fuel Elements
Valentin Casal
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 153-162
Technical Paper | Fuel | doi.org/10.13182/NT80-A32418
Ocean Dumping of High-Level Waste—An Acceptable Solution We Can “Guarantee”
Bernard Cohen
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 163-172
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32419
Laboratory Simulation of High-Level Liquid Waste Evaporation and Storage
Philip A. Anderson
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 173-180
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32420
Effects of Temperature Changes on the Swelling Behavior of 20% Cold-Worked AISI Type 316 Stainless Steel
J. P. Foster, A. Boltax
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 181-188
Technical Paper | Material | doi.org/10.13182/NT80-A32421
Analysis of 60Co Gamma-Ray Transport Through Air by Discrete-Ordinates Transport Codes
Nobuo Sasamoto, Kiyoshi Takeuchi
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 189-199
Technical Paper | Shielding | doi.org/10.13182/NT80-A32422
Radiation Transport in Earth for Neutron and Gamma-Ray Point Sources Above an Air-Ground Interface
R. A. Lillie, R. T. Santoro
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 200-207
Technical Paper | Shielding | doi.org/10.13182/NT80-A32423
Determination of the Concentration of Solutes in Liquids by Means of the (n,α) and (n,γ) Reactions
G. U. Greger, K. Schügerl
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 208-212
Technical Paper | Analysis | doi.org/10.13182/NT80-A32424
Accidental Criticality of a Fusion-Fission Hybrid Blanket Design
V. C. Badham, W. E. Kastenberg, G. C. Pomraning, D. Okrent
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 221-233
Technical Paper | Reactor | doi.org/10.13182/NT80-A32428
Deterministic Criteria Versus Probabilistic Analyses: Examining the Single Failure and Separation Criteria
W. W. Weaver
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 234-243
Technical Paper | Reactor | doi.org/10.13182/NT80-A32429
PLENUM-2A, A Program for Transient Analysis of Liquid-Metal Fast Breeder Reactor Outlet Plenums
Juan J. Carbajo, Paul A. Howard
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 244-265
Technical Paper | Reactor | doi.org/10.13182/NT80-A32430
Ultrasonic Inspection of Liquid-Metal Fast Breeder Reactor Steam Generator Duplex Tubing
K. J. Longua, G. K. Whitham, C. C. Allen
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 257-267
Technical Paper | Reactor | doi.org/10.13182/NT80-A32431
Heat Transfer of a Spray Droplet in a Nuclear Reactor Containment
Mitsugu Tanaka
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 268-281
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32432
Containment Response to Postulated Core Meltdown Accidents in the Fast Flux Test Facility
R. D. Gasser, W. T. Pratt
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 282-307
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32433
Evaporative Removal of Sodium from Reactor Components
F. H. Welch, O. P. Steele III
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 308-311
Technical Paper | Fuel | doi.org/10.13182/NT80-A32434
Radionuclide Transport Through Heterogeneous Media
Jörg Hadermann
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 312-323
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32435
Reduction in the Toxicity of Fission Product Wastes Through Transmutation with Deuterium-Tritium Fusion Neutrons
T. A. Parish, J. W. Davidson
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 324-342
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32436
An Improved Evaluation Model for Zircaloy Oxidation
Howard Ocken
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 343-357
Technical Paper | Material | doi.org/10.13182/NT80-A32437
Gas Generation by Self-Radiolysis of Tritiated Waste Materials
W. E. Tadlock, G. C. Abell, R. H. Steinmeyer
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 358-362
Technical Paper | Material | doi.org/10.13182/NT80-A32438
Nondestructive Fissile Isotopic Measurement Technique for Uranium-233–Uranium-235 Fuels Using Prompt and Delayed Fission Neutron Counting
E. J. Allen, S. R. McNeany
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 363-377
Technical Paper | Analysis | doi.org/10.13182/NT80-A32439
An Investigation of Particulate Corrosion Product Transients in the Primary Coolant of the Winfrith Steam Generating Heavy Water Reactor
F. A. Means, R. S. Rodliffe, K. Harding
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 385-396
Technical Paper | Reactor | doi.org/10.13182/NT80-A32392
Tritium and Fissile Fuel Exchange Between Hybrids, Fission Power Reactors, and Tritium Production Reactors
M. Z. Youssef, R. W. Conn, W. F. Vogelsang
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 397-405
Technical Paper | Reactor | doi.org/10.13182/NT80-A32393
Neutron Moderation in Inertial Confinement Fusion Pellets and Effects on Damage and Radioactive Inventory
F. Beranek, R. W. Conn
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 406-411
Technical Paper | Reactor | doi.org/10.13182/NT80-A32394
Shielding Calculations for the Tokamak Fusion Test Reactor Neutral Beam Injectors
R. T. Santoro, R. A. Lillie, R. G. Alsmiller, Jr, J. M. Barnes
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 412-420
Technical Paper | Reactor | doi.org/10.13182/NT80-A32395
Optimum Fuel Loading and Operation Planning for Light Water Reactor Power Stations. Part II: Boiling Water Reactor Case Study
Tsutomu Hoshino
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 421-435
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32396
Optimum Fuel Loading and Operation Planning for Light Water Reactor Power Stations. Part III: Incremental Cost Study
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 436-443
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32397
Plutonium Fuel Cycles in the Spectral Shift Controlled Reactor
F. M. Sider, R. A. Matzie
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 444-450
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32398
Confinement of Ruthenium Oxides Volatilized During Nuclear Fuels Reprocessing
Edward T. Maas, Jr., John M. Longo
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 451-456
Technical Paper | Chemical Processing | doi.org/10.13182/NT80-A32399
Uncertainty Analysis and Thermal Stored Energy Calculations in Nuclear Fuel Rods
Mitchel E. Cunningham, Courtney R. Hann, Anthony R. Olsen
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 457-467
Technical Paper | Fuel | doi.org/10.13182/NT80-A32400
Adsorption of Iodine Species with Ion Exchange Resins in Aqueous Solutions
Chien-Chang Lin, J. J. Younger
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 468-476
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32401
The Oxidation Kinetics of Some Zirconium Alloys in Flowing Carbon Dioxide at High Temperatures
Rajiv Kohli
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 477-484
Technical Paper | Material | doi.org/10.13182/NT80-A32402
Measurement of the Gamma Dose Rate Distribution in a Spent Fuel Assembly with a Thermoluminescent Detector
Akio Ohno, Shojiro Matsuura
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 485-493
Technical Paper | Hot Laboratory | doi.org/10.13182/NT80-A32403
Boundary Conditions for the Geospheric Transport Equation
Auguste Zurkinden
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 494-495
Technical Note | Radioactive Waste | doi.org/10.13182/NT80-A32404
The Effects of Fe-Ni-Co-V Structural Alloys on Fusion Reactor Neutronic Performance
J. M. Barnes, B. L. Bishop, R. T. Santoro, T. A. Gabriel
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 496-498
Technical Note | Material | doi.org/10.13182/NT80-A32405
