Open AccessAdvanced neutron source reactor probabilistic flow blockage assessment
Author(s) -
Chauna Ramsey
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/204263
Subject(s) - probabilistic logic , nuclear engineering , flow (mathematics) , core (optical fiber) , event (particle physics) , nuclear reactor core , environmental science , computer science , engineering , mechanics , physics , artificial intelligence , telecommunications , quantum mechanics
The Phase I Level I Probabilistic Risk Assessment (PRA) of the conceptual design of the Advanced Neutron Source (ANS) Reactor identified core flow blockage as the most likely internal event leading to fuel damage. The flow blockage event frequency used in the original ANS PRA was based primarily on the flow blockage work done for the High Flux Isotope Reactor (HFIR) PRA. This report examines potential flow blockage scenarios and calculates an estimate of the likelihood of debris-induced fuel damage. The bulk of the report is based specifically on the conceptual design of ANS with a 93%-enriched, two-element core; insights to the impact of the proposed three-element core are examined in Sect. 5. In addition to providing a probability (uncertainty) distribution for the likelihood of core flow blockage, this ongoing effort will serve to indicate potential areas of concern to be focused on in the preliminary design for elimination or mitigation. It will also serve as a loose-parts management tool