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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
WIPP improves utility shaft safety, begins infrastructure project
Harrison Western Shaft Sinkers (HWSS), the company drilling a new utility shaft at the Department of Energy’s Waste Isolation Pilot Plant in New Mexico, has retained a safety culture expert following a near-miss accident in the shaft late last year. The safety expert will conduct monthly facilitated discussions with crews working on the shaft to reinforce expectations for identifying concerns regarding unsafe circumstances, according to a recent report by the Defense Nuclear Facilities Safety Board (DNFSB).
Sukesh K. Aghara, Carl A. Beard
Nuclear Technology | Volume 137 | Number 1 | January 2002 | Pages 1-9
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3253
Articles are hosted by Taylor and Francis Online.
A feasibility study of a proliferation-resistant fuel form for commercial power reactors was conducted. An increase in 238Pu is known to increase the heat load in pure plutonium metal. At high 238Pu concentrations in spent fuel, the heat load in the plutonium may be sufficiently high that it will be less desirable for weapons production. An actinide-based fuel is proposed that will increase the ratio of 238Pu/239Pu in spent fuel, leading to a fuel form resistant to diversion for weapons use. Two actinides were considered, 237Np and 241Am, for seeding in low-enriched (3% 235U) uranium oxide fuel. The ORIGEN point depletion code was utilized to calculate time-dependent spent-fuel concentrations of 238Pu, 239Pu, 237Np, 241Am, and other nuclides of interest. The preliminary results show that both 237Np and 241Am in small quantities generate significant 238Pu in spent fuel, and more importantly, both actinide-based fuels shift the 238Pu/239Pu ratio significantly higher at relatively small initial concentrations. Based on a closed-loop actinide-fuel life cycle study, a 237Np-based fuel cycle seems much more sustainable as compared to 241Am. However, 241Am addition to 237Np-based fuel may have benefits in reducing the end-of-cycle deficit of 237Np.