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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
Erbang Hu, Rentai Yao, Zhanrong Gao, Shuxian Wang, Gang Jiang, Jia Yi Chen
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 339-351
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3148
Articles are hosted by Taylor and Francis Online.
A set of deterministic and probabilistic models for estimating the accident washout factor are developed and established based on accident dispersion factor models given by current guidelines. The deterministic washout factor for different time intervals after accident release, the probabilistic washout factor, and the dose corresponding to various pathways are estimated based on the measured meteorological data on the site of a coastal nuclear power plant to be built in the southeastern part of China. The results show that for doses obtained from 0 to 8 h after a design-basis accident release, the external exposure dose from washout deposition given by the deterministic model is ~55% of that from dry deposition and 22% of individual effective dose (except wet deposition dose); the ratios of external exposure dose from washout to that from dry deposition and to effective dose (except wet deposition dose) given by the probabilistic model are ~5.73 and 2.29, respectively.