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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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August 4–7, 2024
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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In-Line Vacuum-Distillation Sodium Sampler
W. H. Olson
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 7-11
Technical Paper | Reactor | doi.org/10.13182/NT71-A15891
How to Make a Profit on Waste Heat
Sam E. Beall, Jr., G. Samuels
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 12-17
Technical Paper | Reactor | doi.org/10.13182/NT71-A15892
Optimization of Nuclear Materials Safeguards Sampling Systems by Dynamic Programming
G. D. Bouchey, B. V. Koen, C. S. Beightler
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 18-25
Technical Paper | Fuel Cycle | doi.org/10.13182/NT71-A15893
Head-End Separation of Triso-Coated Fissile and Fertile Particles for High-Temperature Gas-Cooled Reactors
S. Langer, N. L. Baldwin, H. R. Phillips
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 26-30
Technical Paper | Chemical Processing | doi.org/10.13182/NT71-A15894
Head-End Separation of Biso-Coated Fissile and Fertile Particles for High-Temperature Gas-Cooled Reactors
S. Langer, H. R. Phillips, N. L. Baldwin
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 31-35
Technical Paper | Chemical Processing | doi.org/10.13182/NT71-A15895
An Investigation of Fast-Reactor Fuel Testing in a Thermal Reactor Core
J. C. Carter, H. Greenspan
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 36-45
Technical Paper | Fuel | doi.org/10.13182/NT71-A15896
Reactor Fuel Management Optimization in a Dynamic Environment
D. Elias, F. J. Munno
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 46-55
Technical Paper | Fuel | doi.org/10.13182/NT71-A15897
Surface Heat Flux for Incipient Boiling in Liquid Metal Heat Pipes
Calvin C. Silverstein
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 56-62
Technical Paper | Fuel | doi.org/10.13182/NT71-A15898
Gas-Cooled Fast Breeder Reactor Fuel Rod Design Considerations
W. I. Thompson
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 63-68
Technical Paper | Fuel | doi.org/10.13182/NT71-A15899
Status of the Waste Solidification Demonstration Program
Jack L. McElroy, Albert G. Blasewitz, Kenneth J. Schneider
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 69-82
Technical Paper | Radioactive Waste | doi.org/10.13182/NT71-A15900
Measurement of Cesium Sorption Isotherms in Liquid Sodium
M. H. Cooper, G. R. Taylor
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 83-92
Technical Paper | Material | doi.org/10.13182/NT71-A15901
Carbon-Carbon Materials for Ablative Environments
E. R. Frye
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 93-107
Technical Paper | Material | doi.org/10.13182/NT71-A15902
Reliability of Fluence-Embrittlement Projections for Pressure Vessel Surveillance Analyses
C. Z. Serpan, Jr.
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 108-118
Technical Paper | Material | doi.org/10.13182/NT71-A15903
Some Comments on the Possibility of Thermodynamically Equilibrating Waste Organic Materials with Nuclear Devices
David R. Safrany
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 119-126
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT71-A15904
Subliming Nuclear Microthruster and Its Space Applications
Philip T. Choong, Edward A. Mason
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 127-136
Technical Paper | Aerospace | doi.org/10.13182/NT71-A15905
Effect of Gamma Radiation on LMFBR Subcriticality Measurements Using Noise Analysis
D. P. Roux, A. R. Buhl
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 137-140
Technical Note | Reactor | doi.org/10.13182/NT71-A15906
A Glass Ampoule Sealer
G. J. Pokorny, A. D. Paulsen
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 141-143
Technical Note | Radioisotope | doi.org/10.13182/NT71-A15907
Nuclear Power and the Public
Charles N. Kelber
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 144-145
Department | Book Review | doi.org/10.13182/NT71-A15909
Reactor Operation
Gerald P. Beck
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Page 144
Department | Book Review | doi.org/10.13182/NT71-A15908
Nuclear Heat Transport
H. C. Perkins
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 145-146
Department | Book Review | doi.org/10.13182/NT71-A15910
Alkali Metal Handling and Systems Operation Techniques
James A. Buckham
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Page 146
Department | Book Review | doi.org/10.13182/NT71-A15911
Evaluation of Critical Mass for Open-Cycle Gas-Core Rocket Reactors
Robert E. Hyland
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 152-161
Technical Paper | Reactor | doi.org/10.13182/NT71-A31023
Anomalies in the Analysis of Air-Spaced Arrays
Thomas Gutman
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 162-172
Technical Paper | Reactor | doi.org/10.13182/NT71-A31024
A Risk Estimate for an Urban-Sited Reactor
Harry J. Otway, Ronald K. Lohrding, Morris E. Battat
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 173-184
Technical Paper | Reactor Siting | doi.org/10.13182/NT71-A31025
Pressure Equalization System for Gas-Cooled Fast Breeder Reactor Fuel Elements
Robert J. Campana
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 185-193
Technical Paper | Fuel | doi.org/10.13182/NT71-A31026
An Analytic Model for the Prediction of In-Pile Behavior of Oxide Fuel Rods
E. Duncombe, C. M. Friedrich, W. H. Guilinger
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 194-208
Technical Paper | Fuel | doi.org/10.13182/NT71-A31027
Estimates of Fuel Containment in a Coaxial Flow Gas-Core Nuclear Rocket
Henry A. Putre
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 209-217
Technical Paper | Aerospace | doi.org/10.13182/NT71-A31028
A Hydrogen Monitor for Detection of Leaks in LMFBR Steam Generators
D. R. Vissers, J. T. Holmes, P. A. Nelson, L. G. Bartholme
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 218-225
Technical Paper | Instrument | doi.org/10.13182/NT71-A31029
A Method of Nondestructive Measurement of the Absolute Cumulative Barium-140 Yield of Uranium Irradiated in Thermal and Fast Neutron Spectra
W. Krappel, H. Seufert, D. Stegemann
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 226-234
Technical Paper | Analysis | doi.org/10.13182/NT71-A31030
Experimental Measurement of Gamma Heat in the High Flux Isotope Reactor
R. L. Senn, W. R. Mixon
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 235-240
Technical Paper | Technique | doi.org/10.13182/NT71-A31031
Safety Considerations for Recharge of THOR Spent Fuels in ZPRL
P. S. Weng
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 241-242
Technical Note | Reactor | doi.org/10.13182/NT71-A31032
Investigation of a Device Using Radiation to Charge and Collect Particulate Matter
William Dickter, M. A. Schultz
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 243-245
Technical Note | Radioisotope | doi.org/10.13182/NT71-A31033
Enriched Uranium Metal Criticality Calculations
D. C. Hunt, D. C. Coonfield
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 260-268
Technical Paper | Reactor | doi.org/10.13182/NT71-A31005
Waste Heat and Fog Control
Robert Conn, Lawrence T. Papay
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 269-275
Technical Paper | Reactor | doi.org/10.13182/NT71-A31006
A Practical Approach to Nuclear Criticality Safety II—Critique of a Model
William Bradley Lewis
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 276-280
Technical Paper | Reactor | doi.org/10.13182/NT71-A31007
Probability Treatment of Atmospheric Dispersion for Dose Calculations
Keith Woodard
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 281-289
Technical Paper | Reactor Siting | doi.org/10.13182/NT71-A31008
Safeguards Inspection—An Analysis of Detection Methods and Diversion Strategies
F. Servais, P. Goldschmidt
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 290-297
Technical Paper | Fuel Cycle | doi.org/10.13182/NT71-A31009
In-Flight Coolant Management Considerations for the NERVA Reactor Cooldown
B. Misra, J. H. Altseimer, G. D. Hart
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 298-306
Technical Paper | Aerospace | doi.org/10.13182/NT71-A31010
Density Determinations of Alkali Metals by a Gamma Radiation Attenuation Technique
I. G. Dillon, F. E. LeVert, P. A. Loretan, G. U. Menon, F. M. Siddiqi, H. J. Tarng
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 307-313
Technical Paper | Technique | doi.org/10.13182/NT71-A31011
Two Methods of Determining ppm Quantities of Plutonium-236 in Plutonium-238
F. K. Tomlinson, W. H. Smith, D. W. Eppink, G. R. Hagee
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 314-319
Technical Paper | Technique | doi.org/10.13182/NT71-A31012
The Detection Efficiency Dependence of Subcriticality Measurements by the Polarity Spectral Coherence Method
N. J. Ackermann, Jr., A. R. Buhl
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 320-323
Technical Note | Reactor | doi.org/10.13182/NT71-A31013
Effects of Different Fission Products in the Beta-Gamma Autoradiography
Ciro Candela, Catello F. Cesarano, Gaetano Trezza
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 324-328
Technical Note | Fuel | doi.org/10.13182/NT71-A31014
A Study of Mine Detection by Means of Neutron-Induced Gamma Rays
F. R. Mynatt, R. G. Alsmiller, Jr., L. R. Williams
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 329-331
Technical Note | Radioisotope | doi.org/10.13182/NT71-A31015
Minimum Critical Mass of Uranium-235 Reflected by Natural Uranium in Water
A. W. Gray
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 342-347
Technical Paper | Reactor | doi.org/10.13182/NT71-A30982
Analysis of Mechanical Work Energy for LMFBR Maximum Accidents
Andrew Padilla, Jr.
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 348-355
Technical Paper | Reactor | doi.org/10.13182/NT71-A30983
Static and Pulsed Reactivity Measurements on Large Uranium-235 Fuel Forms in Water
R. L. Currie, P. B. Parks, J. L. Jarriel
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 356-362
Technical Paper | Reactor | doi.org/10.13182/NT71-A30984
The Utility of Ice Cubes as an Absorbent for Gaseous Fission Products
B. A. Soldano, W. T. Ward
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 363-366
Technical Paper | Reactor Siting | doi.org/10.13182/NT71-A30985
Melting Heat Rating of UO2-25 wt% PuO2 Fuels
L. A. Lawrence, J. A. Christensen
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 367-374
Technical Paper | Fuel | doi.org/10.13182/NT71-A30986
Semiempirical Formulas for Gamma-Ray Dose Rates Through Two-Layer Slab Shields
David A. Sharp, A. Carnesale
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 375-380
Technical Paper | Shielding | doi.org/10.13182/NT71-A30987
Activation Analysis of Sodium and Potassium in Solid Propellants
W. H. Barber, O. H. Dengel, R. H. Vogt, C. V. Strain
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 381-387
Technical Paper | Analysis | doi.org/10.13182/NT71-A30988
Characterization of a Diffusion Tube Hydrogen Detector in a Dynamic Sodium System
Prodyot Roy, Douglas N. Rodgers
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 388-392
Technical Paper | Analysis | doi.org/10.13182/NT71-A30989
Thermal Contact Resistance by Reflection of Heat Diffusion Waves
M. J. Robinson, M. Tomšič
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 393-403
Technical Paper | Technique | doi.org/10.13182/NT71-A30990
Comparison of Stainless Steel and Zircaloy-2 as Encapsulation Materials for Californium-252
P. Philbin, F. Senftle, D. Duffey, P. Wiggins, A. G. Evans
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 404-406
Technical Note | Material | doi.org/10.13182/NT71-A30991
Development of a Method of Neutron Radiography of Mixed Oxide Fuels Using Radiographic Analogs
Lutz W. Dahlke, Maurice Robkin
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 407-414
Technical Note | Analysis | doi.org/10.13182/NT71-A30992
