원자력을 이용한 황-요오드 수소생산 공정 중 황산용액을 이송하는 기존의 시스템과 달리 새로운 황산 이송장치는 벨로우즈 박스 내에서 벨로우즈 외측으로 고온 부식성 액체인 황산이 흐르고, 벨로우즈 내측으로는 냉각수가 흐르는 상태에서 주기 운동을 통해 황산용액이 펌핑 되도록 구성된다. 200 ℃ 이상의 고온 부식성 액체인 황산용액을 정량으로 이송할 수 있도록 장치의 주요부품인 벨로우즈 주변의 열해석을 통해 온도분포를 확인하여, 테프론 재질의 벨로우즈의 내식성 및 내열성을 파악하고, 장치의 안전하고 효율적인 운용을 위한 기초자료를 취득하고자 하였으며, 냉각수 입구직경 3 ㎝, 질량유량이 3.9199 ㎏/s로 고정한 경우 벨로우즈의 길이에 관계없이 테프론 변형온도 이하임을 알 수 있었다.

Spent nuclear fuels should be safely stored until being disposed and dry storage system is predominantly used to retain the fuels. Thermal analysis to estimate temperatures of spent nuclear fuel and the storage system should be performed to evaluate whether the temperatures exceed safety limit. Recently, thermal hydraulic analysis with CFD codes is widely used to investigate the temperature of spent nuclear fuel in dry storage. COBRA-SFS is a legacy code based on subchannel analysis code, and its fidelity is verified for evaluating the thermal analysis for licensing a dry cask system. Herein, thermal analysis result based on CFD and COBRA-SFS codes is compared and the Dry Cask Simulator (DCS) is assessed as a benchmark experiment in this study. Extended Storage Collaborating Program (ESCP) led by the Electric Power Research Institute (EPRI) is organized to address the degradation effects of spent nuclear fuel during long-term dry storage, and DCS is the first phase of the program. The dry storage system, containing a single BWR assembly in a canister, was designed to produce validation-quality data for thermal analysis model. ANSYS FLUENT was used to simulate DCS. Simulations were conducted in various decay heat and helium pressure inside the canister. In realistic conditions of decay heat and helium pressure of actual dry cask system, CFD and COBRA-SFS analysis results gave good agreement with experimental measurement. Peak temperatures of channel can, basket, canister and shell predicted by CFD simulation also showed good prediction and the discrepancies were less than 7 K while measurements uncertainty was 7 K. In high decay heat and high pressure condition, however, CFD and COBRA-SFS underestimated peak cladding temperature than experimental results.