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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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Latest News
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
Huajian Chang (State Nuclear Power Technology R&D Cente/Tsinghua Univ), Yuquan Li, Bin Gao, Cheng Li, Yanfang Xue, Nang Wang (State Nuclear Power Technology R&D Center)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1155-1168
The passive safety system is more reliable and simpler than the conventional active safety system. However, the driving force in a passive safety is relatively low, some phenomena and the mechanisms remain unclear, the interactions and the synergistic effects even make the safety analysis complicated. Therefore, it calls a great demand to conduct both the separate and integral effect tests for assessing the passive safety system performance and validating the correlations or models used in the safety analysis codes. In this paper, the passive safety system test activities conducted for AP600, AP1000 and CAP1400 are reviewed. The ROSA, APEX and SPES were used for AP600 and AP1000 PXS integral test, and for CAP1400, the ACME was designed and built based on the previous test experiences. The LST was built for AP600 containment test, and the CERT was built for CAP1400 containment test with the detailed scaling analysis. The ULPU test facilities were used for AP600 and AP1000 IVR tests, and the FIRM used the real RV material for the CAP1400 IVR test. In this work, the main test facilities design and the test results for the passive safety PWR are presented, and the comparisons among the same type test facilities are also given to highlight the improvements of the passive safety tests.