Probabilistic Risk Assessment of Drop Accident of Cask with o-ring seal during On-site Spent Nuclear Fuel Transportation  
Author Jaehyun Ham


Co-Author(s) Belal Al Momani; Robby Christian; Hyun Gook Kang


Abstract PRA (Probabilistic Risk Assessment) of cask drop accident during on-site SNF (Spent Nuclear Fuel) transportation between SFP (Spent Fuel Pool) and wharf in NPP site was done in this research. Modified process of cask storage system was used. Based on modified process with height and state of cask, drop accident scenarios were invented. Bolted metal cask is selected as a target cask, which is composed of four parts: 21 fuel assemblies, cask body, 2 cask lids, and 2 impact limiters. Based on the results of FDR (Fuel Damage Ratio) and Release Fraction from cask to environment (RFc-e) from the simulation of ABAQUS, source term from cask drop accident was calculated. For all stages, side drop was applied. With the source term, risk to each person in LPZ (Low Population Zone) was calculated by Hotspot code. The total risk in LPZ with 45,000 MWD/MTU burn-up SNFs was calculated as 1.906E-06 man-person/transport for rubber o-ring case, and 8.413E-06 for metal o-ring case.


Keywords Probabilistic Risk Assessment, Spent Nuclear Fuel, On-site Transportation, Cask Drop Accident
    Article #:  22353
Proceedings of the 22nd ISSAT International Conference on Reliability and Quality in Design
August 4-6, 2016 - Los Angeles, California, U.S.A.