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The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Yang-Hyun Koo, Byung-Ho Lee, Jae-Yong Oh, Kun-Woo Song
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 337-347
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A4031
Articles are hosted by Taylor and Francis Online.
Based on the high-burnup fuel data available in open literature, a conservative width of high-burnup structure (HBS) in light water reactor UO2 fuel, which can be used for fuel performance and accident analysis or assessment of spent fuel under geological disposal conditions, is proposed as a function of pellet average burnup. For pellet average burnup of 30 to 60 GWd/t U, where the HBS generally increases with burnup because of the accumulation of irradiation damage, a conservative HBS width is given by wHBS = 13.3 (buavg - 30), where wHBS is the HBS width in m and buavg is the pellet average burnup in GWd/t U. For pellet average burnup of 60 to 75 GWd/t U, where microstructural damage caused by irradiation is partly annealed, a conservative HBS width is expressed by wHBS = 2.02 exp(buavg /11.35). In the case of pellet average burnup above 75 GWd/t U up to at least 100 GWd/t U, the HBS width does not exceed some limiting value of 1.5 mm because high temperature in the central region of the fuel pellet has caused an extensive annealing of irradiation damage. In addition, because of significant fission gas release during irradiation up to high burnup, HBS formation might not have expanded to the pellet region whose temperature was lower than the threshold one. Therefore, for this burnup range, a conservative HBS width is given as wHBS = 1500 m.
