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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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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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Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
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A Helium-Cooled, Poloidal Blanket with Ceramic Breeder and Beryllium Multiplier for the Next European Torus
Mario Dalle Donne, Ulrich Fischer, Marko Küchle
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 15-28
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33707
On the Development and Application of Quantitative Methods in Nuclear Reactor Regulation
Leslie Cave, William E. Kastenberg
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 29-42
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33708
BACCHUS-3D/SP, A Computer Program to Describe Transient Three-Dimensional Single Phase Flow in LMFBR Rod Bundles
Maurizio Bottoni, Burkhardt Dorr, Christoph Homann, Dankward Struwe
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 43-67
Technical Paper | Fission Rector | doi.org/10.13182/NT85-A33709
Measurements and Calculations of Reactivity Effects of Material Rearrangements in a Plutonium-Fueled Fast Reactor Rod Lattice
Friedrich Helm, Georg Henneges
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 68-81
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33710
Conceptual Design of a (Pu,U)O2 Core with a Tight Fuel Rod Lattice for an Advanced Pressurized Light Water Reactor
Cornelis H. M. Broeders, Mario Dalle Donne
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 82-95
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33711
Neutron Physics Investigations for Advanced Pressurized Water Reactors
Cornelis H. M. Broeders
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 96-110
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33712
Critical Heat Flux Correlation for Triangular Arrays of Rod Bundles with Tight Lattices, Including the Spiral Spacer Effect
Mario Dalle Donne, Walter Hame
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 111-124
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33713
A New In-Depth Training Concept for Nuclear Power Plant Operator
Klaus Leinemann, Rainer Meyder, Horst Schnauder, Dieter Smidt
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 125-130
Technical Paper | Fission Rector | doi.org/10.13182/NT85-A33714
Analytical Correlations for Rayleigh-Taylor Instability Growth
Helmut Jacobs
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 131-144
Technical Paper | Fusion | doi.org/10.13182/NT85-A33715
A Study of Fuel Removal via Inner Blanket Intersubassembly Gaps During the Disruption Phase of Hypothetical Loss of Flow Accidents in Heterogeneous LMFBR Cores
Peter Royl, Barry D. Ganapol, Charles R. Bell
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 145-161
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33716
An Experimental Investigation of Fuel Expansion During Core Disruptive Accidents in Liquid-Metal Fast Breeder Reactors Using Simulant Materials
Dirk Wilhelm, Leonhard Meyer
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 162-172
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33717
The Role of Vapor Bubble Dynamics During Energetic Power Excursions in Fast Reactor Core Disruptive Accidents
Erhard A. Fischer, Werner Maschek
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 173-186
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33718
In-Pile Observations of Fuel and Clad Relocation During LMFBR Core Disruptive Accidents in the STAR Experiments
Steven A. Wright, Gustav Schumacher, Peter R. Henkel
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 187-216
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33719
Assessment of the Risk Resulting from Postulated Accidents in Nuclear Power Plants: An Interim Report on Advanced Studies
Anton Bayer
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 217-227
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33720
The Possible Role of 235U-Pu Fueled Advanced Pressurized Water Reactors
Rakesh Chawla, Walter Seifritz
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 228-235
Technical Paper | Fuel Cycle | doi.org/10.13182/NT85-A33721
Nuclear Energy for Coal and Steel
Rudolf Schulten
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 236-239
Technical Paper | Fuel Cycle | doi.org/10.13182/NT85-A33722
On the Dissolution of (U,Pu)O2 Solid Solutions with Different Plutonium Contents in Boiling Nitric Acid
Dieter Vollath, Horst Wedemeyer, Helmut Elbel, Elmar Günther
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 240-245
Technical Paper | Chemical Processing | doi.org/10.13182/NT85-A33723
Modeling Changes in the Fission Gas Behavior Code LAKU Based on Recent Analysis of Experiments
L. Väth, Erhard A. Fischer
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 246-257
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33724
Analysis of the Macro- and Microeconomic Aspects of Advanced Pressurized Water Reactors
Peter Klumpp
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 258-271
Technical Paper | Economic | doi.org/10.13182/NT85-A33725
Delay of the Attack of Liquid Steel on Niobium by a Multilayer Coating
Volker Heinzel, Rolf Huber, I. Schub, Gustav Schumacher
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 272-288
Technical Paper | Material | doi.org/10.13182/NT85-A33726
The (n,2n) and (n,3n) Reactions of Lead, A Potential Neutron Amplifier for Fusion Blankets
Samuel Carmona, Shimon Yiftah
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 289-295
Technical Paper | Material | doi.org/10.13182/NT85-A33727
A Review of Improvements of Evaluated Minor Transactinium Isotope Neutron Data, Their Qualification by Integral Experiments, and Remaining Data Requirements
H. Küsters
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 296-313
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT85-A33728
An Efficient Method to Improve Flow Representation Across Abrupt Changes of Cross-Sectional Areas
Philipp Schmuck
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 314-325
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33729
In-Pile Determination of Fuel Disruption Mechanisms Under LMFBR Loss-of- Flow Accident Conditions
Steven A. Wright, Erhard A. Fischer, Peter K. Mast, Gustav Schumacher
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 326-340
Technical Paper | Analyse | doi.org/10.13182/NT85-A33730
Neutron Reaction Rate Measurements as Tests of Diffusion Calculations in a Fast Breeder Blanket Facility
Franklyn M. Clikeman, Sai-Chi Mo, Karl O. Ott, Gary Alan Harms, H. P. Chou, R. H. Johnson
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 341-352
Technical Paper | Analyse | doi.org/10.13182/NT85-A33731
The CABRI Fast Neutron Hodoscope
K. Baumung, K. Böhnel, H. Bluhm
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 353-365
Technical Paper | Technique | doi.org/10.13182/NT85-A33732
Numerical Simulation of Two-Phase Flow in Horizontal Interconnected Subchannels
Mamdouh Shoukri, Abd-El-Elah Tahir, Michael B. Carver
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 375-385
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33690
Analysis of Thermal Reactor Benchmarks with Design Codes Based on ENDF/B-V Data
Mark L. Williams, R. Q. Wright, Brian A. Worley, Odelli Ozer, Walter J. Eich
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 386-401
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33691
A Reactor Water Level and Pressure Prediction Method Under Small Loss-of-Coolant-Accident Conditions in Boiling Water Reactors
Yukiharu Ohga, Kohyu Fukunishi
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 402-410
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33692
Dynamics of Fuel Vapor Pressure Buildup in Voided LMFBR Cores During the Transient Heating and Its Effect on the Energy Release in a Core Disruptive Accident
Om Pal Singh, P. Bhaskar Rao
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 411-416
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33693
Purex Diluent Chemical Degradation
O. K. Tallent, J. C. Mailen, K. E. Dodson
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 417-425
Technical Paper | Chemical Processing | doi.org/10.13182/NT85-A33694
Experimental Investigation of the Iodine Partition Coefficient
James L. Kelly, Robert U. Mulder, Chaim J. Babad
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 426-429
Technical Paper | Chemical Processing | doi.org/10.13182/NT85-A33695
Graphite Disk UO2 Fuel Elements Designed for Extended Burnups at High Powers
Roderick D. MacDonald, Ian J. Hastings
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 430-444
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33696
Statistical Patterns of Fuel Failure in Stainless Steel Clad Light Water Reactor Fuel Rods
Gary S. Was, Ronald Christensen, Chang Park, Richard W. Smith
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 445-457
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33697
Diffusivities of Some Constituents in Compacted Wet Bentonite Clay and the Impact on Radionuclide Migration in the Buffer
Ivars Neretnieks
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 458-470
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33698
A Pilot-Scale Radioactive Test Using In Situ Vitrification
Craig L. Timmerman, Ken H. Oma
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 471-481
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33699
Dilute Chemical Decontamination Process for Pressurized and Boiling Water Reactor Applications
Alexander P. Murray, David A. Eckhardt, Sharon L. Weisberg
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 482-496
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33700
A High-Performance Neutron Time Correlation Counter
H. O. Menlove, J. E. Swansen
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 497-505
Technical Paper | Analyses | doi.org/10.13182/NT85-A33701
An Iterative Correction Method for Nondestructive Plutonium Waste Assay
Minsun Ouyang
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 506-511
Technical Paper | Analyses | doi.org/10.13182/NT85-A33702
Computer Graphics to Separate Neutron from Gamma-Ray Spectra, Applied to the Measurement of Neutron Attenuation Coefficients Using an NE-213 Scintillator
Martin E. Nelson, Dean A. Miller, Peter F. Wiggins, Gordon Riel, Thomas D. Strickler
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 512-519
Technical Paper | Technique | doi.org/10.13182/NT85-A33703
A Fluidized-Bed Nuclear Reactor Concept
Farhang Sefidvash
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 527-534
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33675
Automatic Optimized Reload and Depletion Method for a Pressurized Water Reactor
Dawk Hwan Ahn, Samuel H. Levine
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 535-547
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33676
An Axially and Radially Two-Zoned Large Liquid-Metal Fast Breeder Reactor Core Concept
Takanobu Kamei, Mitsuaki Yamaoka, Yasuyuki Moriki, Masao Suzuki, Kazuo Arie
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 548-556
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33677
A Correlation Between Operation of Primary Coolants at Low pHT with Steam Generator Channel Head Dose Rates in Westinghouse Pressurized Water Reactors
Martin Victor Polley
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 557-567
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33678
A Mathematical Method for Boiling Water Reactor Control Rod Programming
Shinji Tokumasu, Michihiro Ozawa, Hiroshi Hiranuma, Michiro Yokomi
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 568-579
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33679
A Symptom-Oriented Method for Posttrip Operation Guidance in Boiling Water Reactors
Junichi Tanji, Shunsuke Utena
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 580-589
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33680
Experimental and Theoretical Investigations of Corrosion Mechanisms in Cemented Waste Forms
Bernhard Kienzler, Rainer H. Köster
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 590-596
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33681
Radiation Dose Deposition and Colloid Formation in a Rock Salt Waste Repository
Jitze Bergsma, Robert B. Helmholdt, Roel J. Heijboer
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 597-607
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33682
Thermal Compatibility Studies of Unirradiated Uranium Silicide Dispersed in Aluminum
T. C. Wiencek, R. F. Domagala, H. R. Thresh
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 608-616
Technical Paper | Material | doi.org/10.13182/NT85-A33683
Three-Dimensional Neutron Streaming Analysis Using the Monte Carlo Coupling Technique in a Medical Irradiation Room of the Musashi Reactor: Comparison with Experiments
Yoshiko Harima, Kohtaro Ueki, Otohiko Aizawa
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 617-627
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT85-A33684
Analyses of ROSA-III Break Area Spectrum Experiments on a Boiling Water Reactor Loss-of-Coolant Accident
K. Tasaka, Y. Koizumi, Y. Kukita, H. Nakamura, Y. Anoda, M. Iriko, H. Kumamaru, M. Suzuki
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 628-643
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33685
A Simple Computer Model of Pellet/Cladding Interaction Including Stress Corrosion Cracking
James Y. Yaung, D. Okrent, A. R. Wazzan
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 644-650
Technical Note | Nuclear Fuel | doi.org/10.13182/NT85-A33686
