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  How does subsequent license renewal relate to the restart of nuclear power plants?
  Gary Adkins
  Subsequent license renewal (SLR) authorizes nuclear power plants to operate for an additional 20 years beyond the 60 years of the initial license (years 1–40) and the first license renewal (years 41–60). NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR), and NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications (SRP-SLR), were issued in July 2017 and provide guidance for generic evaluation of plant aging management programs and reviews of SLR applications, respectively, by Nuclear Regulatory Commission staff.
  The first SLR application was submitted to the NRC for review in January 2018. A total of 10 additional SLR applications addressing 20 operating units have been submitted to the NRC. Nine operating units have been approved by the NRC, and 13 units are under review. These 22 units do not have any issues, including operating experience issues, precluding them from achieving a renewed license.
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Code Development and Target Station Design for Chinese Accelerator-Driven System Project

Han-Jie Cai, Fen Fu, Jian-Yang Li, Ya-Ling Zhang, Xun-Chao Zhang, Xue-Song Yan, Zhi-Lei Zhang, Jian-Ya Xv, Mei-Ling Qi, Lei Yang

Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 107-115

Technical Paper | doi.org/10.13182/NSE15-59

First Online Publication:March 10, 2016

Updated:May 3, 2016

Articles are hosted by Taylor and Francis Online.

The Institute of Modern Physics, Chinese Academy of Sciences performs research and development on the target station of an accelerator-driven system (ADS) under the China ADS project. A newly developed Monte Carlo program for the design of the target station named GMT1.0 is presented. The program is designed for a massively parallelized simulation of the initiative granular-flow target concept. Based on the combination of the Intranuclear Cascade of Leige (INCL) model and the ABLA evaporation/fission model, GMT1.0 integrates a particle transport code and a nuclear reaction code to simulate a spallation target. For validation, a series of calculations of neutronics characteristics and heat-deposit distributions of solid targets were performed, and a high degree of accuracy was shown for GMT1.0. Using GMT1.0, a systematic study of the neutron economy of the target was performed and the neutronics characteristics of the most optimal parameters were illustrated well.