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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Tenth International RETRAN Conference Overview: RETRAN's Role in Supporting the Nuclear Industry's Vision
Lance J. Agee
Nuclear Technology | Volume 142 | Number 1 | April 2003 | Pages 3-9
Technical Paper | RETRAN | doi.org/10.13182/NT03-A3369
RETRAN-3D MOD003 Peach Bottom Turbine Trip 2 Multidimensional Kinetics Analysis Models and Results
Michitsugu Mori, Katsunori Ogura, Garry C. Gose, Jen-Ying Wu
Nuclear Technology | Volume 142 | Number 1 | April 2003 | Pages 10-18
Technical Paper | RETRAN | doi.org/10.13182/NT03-A3370
The Analysis of Pressurized Water Reactor and Boiling Water Reactor Reactivity Transients with CORETRAN and RETRAN-3D
Hakim Ferroukhi, Paul Coddington
Nuclear Technology | Volume 142 | Number 1 | April 2003 | Pages 19-34
Technical Paper | RETRAN | doi.org/10.13182/NT03-A3371
Application of the IBERDROLA RETRAN Licensing Methodology to the Confrentes BWR-6 110% Extended Power Uprate
Rafael de la Fuente, Javier Iglesias, Pablo G. Sedano, Pedro Mata
Nuclear Technology | Volume 142 | Number 1 | April 2003 | Pages 35-46
Technical Paper | RETRAN | doi.org/10.13182/NT03-A3372
Assessment of RETRAN-3D Boiling Models Against Experimental Subcooled Boiling Tube Data
Rafael Macian, Paul Coddington, Paul Stangroom
Nuclear Technology | Volume 142 | Number 1 | April 2003 | Pages 47-63
Technical Paper | RETRAN | doi.org/10.13182/NT03-A3373
Evaluation of the RETRAN-3D Wall Friction Models and Heat Transfer Coefficient Correlations
Craig E. Peterson, John G. Shatford, James F. Harrison, Lance J. Agee
Nuclear Technology | Volume 142 | Number 1 | April 2003 | Pages 64-76
Technical Paper | RETRAN | doi.org/10.13182/NT03-A3374
Thermal-Hydraulic Analysis of the Nuclear Power Engineering Corporation Containment Experiments with GOTHIC
Lawrence E. Wiles, Thomas L. George
Nuclear Technology | Volume 142 | Number 1 | April 2003 | Pages 77-91
Technical Paper | RETRAN | doi.org/10.13182/NT03-A3375
Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations
Kostadin N. Ivanov, Nadejda K. Todorova, Enrico Sartori
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 95-115
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3376
Effects of Secondary Circuit Modeling on Results of Pressurized Water Reactor Main Steam Line Break Benchmark Calculations with New Coupled Code TRAB-3D/SMABRE
Antti Daavittila, Anitta Hämäläinen, Riitta Kyrki-Rajamäki
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 116-123
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3377
Analysis of the Pressurized Water Reactor Main Steam Line Break Benchmark by the Coupled Code System ATHLET-QUABOX/CUBBOX
Siegfried Langenbuch, Klaus-Dieter Schmidt, Kiril Velkov
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 124-136
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3378
Sensitivity Studies for Main Steam Line Break Exercises 2 and 3 with RELAP5/PANBOX
Rainer Böer, Alfred Knoll
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 137-145
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3379
Analyses of the OECD Main Steam Line Break Benchmark with the DYN3D and ATHLET Codes
Ulrich Grundmann, Sören Kliem
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 146-153
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3380
CEA-IRSN Participation in the Main Steam Line Break Benchmark
E. Royer, E. Raimond, D. Caruge
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 154-165
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3381
Analysis of the OECD Main Steam Line Break Benchmark Problem Using the Refined Core Thermal-Hydraulic Nodalization Feature of the MARS/MASTER Code
Han Gyu Joo, Jae-Jun Jeong, Byung-Oh Cho, Won Jae Lee, Sung Quun Zee
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 166-179
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT142-166
Three Mile Island Unit 1 Main Steam Line Break Three-Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes
Francesco D'Auria, José Luis Gago Moreno, Giorgio Maria Galassi, Davor Grgic, Antonino Spadoni
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 180-204
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3383
Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTRÉE
Akitoshi Hotta, Takafumi Anegawa, Takashi Hara, Hisashi Ninokata
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 205-229
Technical Paper | Fission Reactors | doi.org/10.13182/NT03-A3384
The Neutronics Design and Analysis of a 200-MW(electric) Simplified Boiling Water Reactor Core
Daniel R. Tinkler, Thomas J. Downar
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 230-242
Technical Paper | Fission Reactors | doi.org/10.13182/NT02-47
Basic Considerations on Defining Safety Goals
Tadakuni Hakata
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 243-249
Technical Paper | Reactor Safety | doi.org/10.13182/NT03-A3386
Investigation of Irradiation Behavior of SiC-Coated Fuel Particle at Extended Burnup
Kazuhiro Sawa, Tsutomu Tobita
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 250-259
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT03-A3387
Out-of-Pile Properties of Hyperstoichiometric (U0.45Pu0.55)C Fuel for the Fast Breeder Test Reactor
A. K. Sengupta, J. Banerjee, T. Jarvis, T. R. G. Kutty, K. Ravi, S. Majumdar
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 260-269
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT03-A3388
Experimental and Numerical Investigations on Debris Bed Coolability in a Multidimensional and Homogeneous Configuration with Volumetric Heat Source
Kresna Atkhen, Georges Berthoud
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 270-282
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3389
Taming the Crud Problem: A Utility Perspective
Yovan D. Lukic, Jeffrey S. Schmidt
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 283-293
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT03-A3390
Study of the Consequences of Secondary Water Radiolysis Surrounding a Defective Canister
Jinsong Liu, Ivars Neretnieks, Bo H. E. Strömberg
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 294-305
Technical Paper | Radioisotopes | doi.org/10.13182/NT03-A3391
Heterogeneous Target to Reduce the Toxicity of Spallation Products in an Accelerator-Driven System
Alexey Yu. Stankovsky, Vladimir V. Artisyuk, Masaki Saito
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 306-317
Technical Paper | Accelerators | doi.org/10.13182/NT03-A3392
