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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Plans for the Bruce C project in Ontario open for public comment
As Bruce Power continues predevelopment work, public input is being sought on the potential Bruce C nuclear power expansion project in Ontario.
Bruce Power recently submitted its initial project description to the Impact Assessment Agency of Canada for an expansion that would add up to 4,800 MWe. Earlier this year, the Canadian government announced up to C$50 million ($36.8 million) in funding for the Bruce C project, which would be Canada’s first major expansion of a large nuclear plant in decades.
Gordon M. Lodde, Beverly A. Good, Diane M. Surgeoner
Nuclear Technology | Volume 87 | Number 2 | October 1989 | Pages 535-544
Technical Paper | TMI-2: Health Physics and Environmental Release / Nuclear Safety | doi.org/10.13182/NT89-A27750
Articles are hosted by Taylor and Francis Online.
As a result of the March 28, 1979, accident at Three Mile Island Unit 2 (TMI-2), significant quantities of fission gases and volatile radionuclides, primarily radioiodine, were released into the enclosed reactor building (RB) atmosphere from the damaged reactor core. Approximately 1 yr after the accident, air samples of the RB atmosphere showed that 85Kr was the principle remaining radionuclide. The TMI-2 controlled venting experience proved that radioactive gases released during an accident causing significant core damage can be safely disposed of through atmospheric dispersion after a suitable period for radioactive decay of short-lived radioactive contaminants. The actions taken by the use of ice vests and the installation of air chillers provided a tolerable working environment within the RB for workers dressed in protective clothing. The contribution of the doses due to internally deposited radioactivity has been negligible when compared to those for radiation sources outside the body. It is clear that uptakes of radioactive material into the body have not been significant at TMI-2.