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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
L. Cantrel
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 11-28
Technical Paper | Reactor Safety | doi.org/10.13182/NT156-11
Articles are hosted by Taylor and Francis Online.
Iodine is a fission product of major importance because volatile species can be formed under severe nuclear reactor accident conditions and may potentially be released into the environment, leading to significant radiological consequences. The CAIMAN program was devoted to studying the radiochemistry of iodine in the reactor containment in the case of a severe accident occurring in a pressurized water reactor; this is a database of prime importance for the validation of codes, namely IODE, which is a module of the integral Accident Source Term Evaluation Code (ASTEC), jointly developed by the Institut de Radioprotection et de Sûreté Nucléaire and the Gesellschaft für Anlagen- und Reaktorsicherheit. These computations are generally used to predict the radiological consequences of such an accident.The experimental program, which ran from 1996 to 2002, concerned 18 experiments in a facility of intermediate scale (300 dm3), where labeled iodine, 131I, was used to perform gamma counting. The CAIMAN tests are here analyzed, and the main experimental observations and trends are described. For each experiment, IODE computations were performed and compared with experimental results in order to assess the possible weak points of the present modeling and to identify key parameters. Broadly speaking, the gaseous concentrations predicted are quite consistent with the experimental ones; the remaining gaps have been identified.