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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
P. Barbucci, L. Bella
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 1-8
Technical Paper | Fission Reactor | doi.org/10.13182/NT95-A15847
Articles are hosted by Taylor and Francis Online.
The results of a simulation activity on a General Electric (GE) simplified boiling water reactor (SB WR) carried out at ENEL (the Italian Electricity Board) are discussed. The SBWR is a medium-size [600 MW(electric)] new generation reactor developed by GE, whose safety is ensured by means of passive systems (water gravity injection, pressure suppression, and passive heat removal). The RELAP5/MOD2 code is a well-known tool developed at the Idaho National Engineering Laboratories and made available by the U.S. Nuclear Regulatory Commission; it has been widely used and qualified all over the world. To investigate the thermal-hydraulic performance of such an innovative reactor during accident scenarios, a SBWR RELAP5/MOD2 model was developed and a selected number of transients were analyzed. The typical phenomena related to the SBWR accident behavior was investigated. A good agreement was found between the RELAP5/MOD2 code and the licensing code (TRAC-G) results. In all cases, the performance of the SBWR safety systems was also evaluated.