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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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First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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Simulation of the OECD Main-Steam-Line-Break Benchmark Exercise 3 Using the Coupled RELAP5/PANTHER Codes
Christophe R. Schneidesch, Jinzhao Zhang
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 1-14
Technical Paper | Reactor Safety | doi.org/10.13182/NT04-A3482
Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark
Tomasz Kozlowski, R. Matthew Miller, Thomas J. Downar, Douglas A. Barber, Han Gyu Joo
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 15-28
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3483
Methods and Results for the MSLB NEA Benchmark Using SIMTRAN and RELAP-5
José M. Aragonés, Carol Ahnert, Oscar Cabellos, Nuria García-Herranz, Vanessa Aragonés-Ahnert
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 29-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3484
Analysis of a Main-Steam-Line Break in Ascó NPP
Arántzazu Cuadra, José-Luis Gago, Francesc Reventós
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 41-48
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3485
Analytical Study on Fire and Explosion Accidents Assumed in HTGR Hydrogen Production System
Yoshitomo Inaba, Tetsuo Nishihara, Yoshikazu Nitta
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 49-57
Technical Paper | Reactor Safety | doi.org/10.13182/NT04-A3486
Calculations of the Neutron Flux Outside BWR 8 × 8 Spent-Fuel Assemblies and the Sensitivity to Fuel Pin Diversion
Peter Jansson, Ane Håkansson, Anders Bäcklin
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 58-64
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3487
A Neural Network Model for the Tomographic Analysis of Irradiated Nuclear Fuel Rods
Teddy Craciunescu
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 65-71
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3488
Isotopic Transmutations in Irradiated Beryllium and Their Implications on MARIA Reactor Operation
Krzysztof J. Andrzejewski, Teresa A. Kulikowska
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 72-82
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT04-A3489
Counter-Permeation of Deuterium and Hydrogen Through INCONEL 600®
Tetsuaki Takeda, Jin Iwatsuki
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 83-95
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT04-A3490
Analysis of Seven NEPTUN-III (Tight-Lattice) Bottom-Flooding Experiments with RELAP5/MOD3.3/BETA
G. Th. Analytis
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 99-121
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3491
A Study of Boron and Temperature Mixing in the Downcomer and the Lower Part of a VVER Reactor Vessel
Yury A. Bezrukov, Sergey A. Logvinov, Vladimir N. Ul'yanovsky, Nikolay A. Strebnev
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 122-130
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3492
Development and Validation of ARKAS_cellule: An Advanced Core-Bowing Analysis Code for Fast Reactors
Hirokazu Ohta, Takeshi Yokoo, Masatoshi Nakagawa, Shinichiro Matsuyama
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 131-142
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3493
Criticality Data for Spherical 235U, 239Pu, and 237Np Systems Reflector-Moderated by Low Capturing-Moderator Materials
David J. Loaiza, William Stratton
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 143-154
Technical Paper | Reactor Safety | doi.org/10.13182/NT04-A3494
Advanced MOX Core Design Study of Sodium-Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan
Tomoyasu Mizuno, Hajime Niwa
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 155-163
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-4
Mechanical Analysis of High Power Internally Cooled Annular Fuel
Jiyun Zhao, Hee Cheon No, Mujid S. Kazimi
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 164-180
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3496
Decision Analysis and Its Application to the Frequency of Containment Integrated Leakage Rate Tests
George E. Apostolakis, John P. Koser, Gaku Sato
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 181-198
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3497
Analysis of PWR RCS Injection Strategy During Severe Accident
Shih-Jen Wang, Kwang-Sheng Chiang, Show-Chyuan Chiang
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 199-205
Technical Note | Reactor Safety | doi.org/10.13182/NT04-A3498
A Simple Kinetic Model for the Alpha Radiolysis of Water Sorbed on NpO2
Alan S. Icenhour, Louis M. Toth, Robert M. Wham, R. R. Brunson
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 206-209
Technical Note | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3499
Effect of Replacing Helium with a Liquid Metal in the Fuel-Cladding Gap on Fission Gas Release
Doonyapong Wongsawaeng, Donald R. Olander
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 211-220
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3500
A Simplified Approach for Evaluation of the Burnup Potential of Alternative Fuels
Stella Maris Oggianu, Hee Cheon No, Mujid S. Kazimi
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 221-229
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3501
WISE: A New Fuel Cycle Concept Based on a Mobile Fuel Reactor
Igor Slessarev, G. Palmiotti, M. Salvatores, V. Berthou
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 230-243
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3502
Investigating the Nonlinear Dynamics of Natural-Circulation, Boiling Two-Phase Flows
Robert Zboray, Wilhelmus J. M. de Kruijf, Tim H. J. J. van der Hagen, Rizwan-uddin
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 244-256
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3503
IIST Passive Core Cooling on Pressurizer Top Break
Tay-Jian Liu, Chien-Hsiung Lee
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 257-266
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3504
Multilevel Methodology in Parallel Computing Environment for Evaluating BWR Safety Parameters
Jorge Solís, Maria N. Avramova, Kostadin N. Ivanov
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 267-278
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3505
Experimental Validation of CFD Analyses for Estimating the Transport Fraction of LOCA-Generated Insulation Debris to ECCS Sump Screens
Arup K. Maji, Bruce Letellier, Kyle W. Ross, Daseri V. Rao, Luke Bartlein
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 279-289
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3506
A Fuzzy Modeling Approach to Road Transport with Application to a Case of Spent Nuclear Fuel Transport
Marzio Marseguerra, Enrico Zio, Mauro Bianchi
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 290-302
Technical Paper | Criticality of Nuclear Materials | doi.org/10.13182/NT04-A3507
Radiation Shielding Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)
Gyuhong Roh, Hangbok Choi
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 303-324
Technical Paper | Radiation Protection | doi.org/10.13182/NT04-A3508
The Use of Molybdenum-Based Ceramic-Metal (CerMet) Fuel for the Actinide Management in LWRs
Klaas Bakker, Frodo C. Klaassen, Ronald P. C. Schram, Alfred Hogenbirk, Robin Klein Meulekamp, Arjan Bos, Hubert Rakhorst, Charles A. Mol
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 325-331
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT04-A3509
