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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
Latest Magazine Issues
Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
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Simulation of Maanshan TMLB' Sequence with MELCOR 1.8.3
Shih-Jen Wang, Chun-Sheng Chien, Te-Chuan Wang
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 1-9
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2954
A Study on Boiling Water Reactor Stability Behavior
Dieter Hennig
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 10-31
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2955
Reload Light Water Reactor Core Designs for an Ultralong Operating Cycle
Michael V. McMahon, Michael J. Driscoll, Edward E. Pilat, Neil E. Todreas
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 32-47
Technical Paper | Fuel Cycle And Management | doi.org/10.13182/NT99-A2956
Using an IIST SBLOCA Experiment to Assess RELAP5/MOD3.2
Chien-Hsiung Lee, I-Ming Huang, Chin-Jang Chang, Tay-Jian Liu, Yuh-Ming Ferng
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 48-61
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2957
Hand Calculation of Safe Separation Distances Between Natural-Gas Pipelines and Boilers and Nuclear Facilities in the Hanford Site 300 Area
Philip M. Daling, Tonia M. Graham
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 62-74
Technical Paper | Criticality of Nuclear Materials | doi.org/10.13182/NT99-A2958
Pitfalls in the Use of Solubility Limits for Radioactive Waste Disposal: The Case of Nickel in Sulfidic Groundwaters
Tres Thoenen
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 75-87
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A2959
DART Model for Irradiation-Induced Swelling of Uranium Silicide Dispersion Fuel Elements
Jeffrey Rest, Gerard L. Hofman
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 88-101
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT99-A2960
A System of 99mTc Production Based on Distributed Electron Accelerators and Thermal Separation
Ralph G. Bennett, Jerry D. Christian, David A. Petti, William K. Terry, S. Blaine Grover
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 102-121
Technical Paper | Radioisotopes | doi.org/10.13182/NT99-A2961
Experimental and Analytical Investigation of the Operation Mode of the Emergency Condenser of the SWR1000
Andreas Schaffrath, E. F. Hicken, H. Jaegers, H.-M. Prasser
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 123-142
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2962
Assessment of the Severe Accident Mitigation Features of the European Pressurized Water Reactor by Cooperative Research and Development
Wolfgang Eglin, Ulrich Krugmann, Horst A. Weisshäupl, Werner Scholtyssek
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 143-152
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2963
FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package
Brian R. Moore, Paul J. Turinsky, Atul A. Karve
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 153-169
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A2964
Evaluating Code Uncertainty - I: Using the CSAU Method for Uncertainty Analysis of a Two-Loop PWR SBLOCA
Andrej Prosek, Borut Mavko
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 170-185
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2965
Evaluating Code Uncertainty - II: An Optimal Statistical Estimator Method to Evaluate the Uncertainties of Calculated Time Trends
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 186-195
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2966
Studies on the Shielding Properties of Polyboron and Ilmenite-Magnetite Concrete Using a Reactor Neutron Beam
F. U. Ahmed, S. I. Bhuiyan, A. S. Mollah, M. R. Sarder, M. Q. Huda, M. Rahman, M. A. W. Mondal
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 196-204
Technical Paper | Radiation | doi.org/10.13182/NT99-A2967
Self-Excited Plutonium X-Ray Emission in Plutonium-Bearing Materials
Franco Vittorio Frazzoli, Romolo Remetti, Sergio Guardini, Valeri Maiorov
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 205-214
Technical Paper | Reprocessing | doi.org/10.13182/NT99-A2968
The Volatility of Iodine from Irradiated Iodide Solutions in the Presence or Absence of Painted Surfaces: Modeling Work on the IODE Code at IPSN
Christian Poletiko, Didier Jacquemain, Claude Hueber
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 215-228
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT99-A2969
Analysis of the Mass Transfer Characteristics of a Chemical Addition System
Byong Hoon Chang, Chang Kyu Chung, Anthony F. Mills
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 229-236
Technical Note | Reactor Operations and Control | doi.org/10.13182/NT99-A2970
An Empirical Equation for Vapor Pressure of Tri-n-Butyl Phosphate in the Temperature Range of 273.15 to 562.15 K
Shekhar Kumar, S. B. Koganti
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 237-239
Technical Note | Reprocessing | doi.org/10.13182/NT99-A2971
Boundary-Layer-Boiling and Critical-Heat-Flux Phenomena on a Downward-Facing Hemispherical Surface
Fan-Bill Cheung, K. H. Haddad, Y. C. Liu
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 243-264
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2972
Plant Behavior Following a Loss-of-Residual-Heat-Removal Event Under a Shutdown Condition
Kwang Won Seul, Young Seok Bang, Hho Jung Kim
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 265-278
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2973
Monte Carlo Approach to the Detectability of a Gamma Source Within a Scrap-Iron Truckload
Marzio Marseguerra, Enrico Zio
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 279-288
Technical Paper | Radiation | doi.org/10.13182/NT99-A2974
Behavior of Uranium and Zirconium in Direct Transport Tests with Irradiated EBR-II Fuel
Rajesh Ahluwalia, Thanh Q. Hua, Howard K. Geyer
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 289-302
Technical Paper | Reprocessing | doi.org/10.13182/NT99-A2975
Criticality Safety Assessment for a Conceptual High-Level-Waste Repository in Water-Saturated Geologic Media
Joonhong Ahn
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 303-318
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A2976
A Physical Model to Predict Wear Sites Engendered by Flow-Assisted Corrosion
Yuh-Ming Ferng, Yin-Pang Ma, Kuo-Tong Ma, Nien-Mien Chung
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 319-330
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT99-A2977
RELAP5/MOD3 Code Analyses of LSTF Experiments on Intentional Primary-Side Depressurization Following SBLOCAs with Totally Failed HPI
Hiroshige Kumamaru, Yutaka Kukita, Hideaki Asaka, Ming Wang, Etsuo Ohtani
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 331-339
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT99-A2978
Protection System of the New Control Console of a TRIGA Mark III Nuclear Research Reactor
Tonatiuh Rivero-Gutiérrez, Eduardo Sáinz-Mejía, Jorge S. Benítez-Read, José L. González-Marroquín
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 340-347
Technical Note | Reactor Operations and Control | doi.org/10.13182/NT99-A2979
