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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.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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Nuclear Science and Engineering
Fusion Science and Technology
First container of test glass filled at Hanford’s Vit Plant
Bechtel and the Department of Energy’s Office of Environmental Management announced on December 4 that the first set of test glass was successfully poured into a stainless-steel storage container designed to hold vitrified waste at Hanford’s Waste Treatment and Immobilization Plant, also known as the Vit Plant.
Julien Beaucourt, Gabriel Georgescu
Nuclear Technology | Volume 207 | Number 3 | March 2021 | Pages 323-334
Technical Paper | doi.org/10.1080/00295450.2020.1770530
Articles are hosted by Taylor and Francis Online.
Extension of the operational lifetime beyond 40 years is currently a noteworthy project in the field of nuclear safety in France, especially for 900-MW(electric) reactors that will be the first ones to go through the fourth periodic safety review. For 1300-MW(electric) reactors, the safety studies have already been engaged. Probabilistic Safety Assessments (PSAs) play an important role in this process, including assessment of the robustness of the plants against internal and external hazards. Among the hazards, internal explosion induced by hydrogen accumulation due to leakage of pipes and/or singularities, or failure of venting systems in the battery rooms is now taken into account in the PSA developed by the licensee (EDF). The PSAs are then reviewed by IRSN, which is the French Technical support organization. To achieve this purpose, IRSN develops its own Level 1 PSA studies. This paper takes into account the most recent developments of the IRSN analyses, especially regarding the Bayesian quantification of the hydrogen leak frequency derived from an original method developed by Sandia National Laboratories.