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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
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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.”
Shunsuke Uchida, Masanori Naitoh, Hiroaki Suzuki, Hidetoshi Okada, Satoshi Konishi
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 252-265
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-152
Articles are hosted by Taylor and Francis Online.
As a result of the mass balance analysis for fission products (FPs) in the contaminated water accumulated in the Fukushima Daiichi nuclear power plant in the aftermath of the accident, it was concluded that the short-term cesium source was 50% of the total amount of cesium accumulated in the reactor, which was estimated with the SAMPSON severe accident analysis code, while the short-term source of tritium was 26% of the total tritium that was released during the UO2 fuel meltdown. The FP concentrations in the contaminated water during the 2 yr since the accident were determined by short-term FP sources, while their saturated concentrations, due to a balance between the release from the reactor and the cleanup, were determined by long-term FP sources. A multinuclei removal system, ALPS, has been operated at the plant to clean up the contaminated water to reduce FP concentrations to a level that is permitted for release to the environment. Tritium concentration in the contaminated water decreased a little during the 2 yr since the accident primarily from dilution by mixing groundwater rather than intentional removal. Industrial-scale removal of tritium from the huge amount of contaminated water is almost impossible using isotopic separation methods. Storage of tritiated water for a long period presents a high risk for leakage to the environment. As the most realistic procedure, the authors propose that the tritium be diluted with plenty of seawater to the natural background level and then be released into the ocean with continuous monitoring at the release point.