Speaker
Dr
Sanghoon Lee
(Korea Atomic Energy Research Institute)
Description
In preparation for the timely installation of interim storage facility for spent nuclear fuel (SF), Korea Radioactive Waste Agency (KORAD) is developing domestic models of SF storage systems, and the concrete storage cask is one of them. A concrete cask consists of a metallic canister, which confines SF with welded closure and a concrete overpack, which provides radiation shielding and physical protection to the canister. The safety requirements for a SF storage cask is well established in the US, and summarized in regulatory guides such as NUREG-1536. Korea Atomic Energy Research Institute (KAERI) has been performing tests of the concrete cask to demonstrate its safety and compliance to the regulatory requirements with high priority stipulated in NUREG-1536. The test program includes the structural performance tests under a tip-over and earthquake, and decay heat removal test under normal, off-normal, and accident conditions. In this paper, a brief introduction to the test program and test results are provided.
Country/ int. organization
Korea/Korea Atomic Energy Research Institute
Primary author
Dr
Sanghoon Lee
(Korea Atomic Energy Research Institute)
Co-authors
Mr
Ju-Chan Lee
(Korea Atomic Energy Research Institute)
Dr
Kiseog Seo
(Korea Atomic Energy Research Institute)
Mr
Kyung-Sik Bang
(Korea Atomic Energy Research Institute)
Dr
Sang-Soon Cho
(Korea Atomic Energy Research Institute)
Dr
Seung-Hwan Yu
(Korea Atomic Energy Research Institute)
Dr
Woo-Seok Choi
(Korea Atomic Energy Research Institute)
