Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects


Zabunoolu O. H. , Yavuz U.

KERNTECHNIK, vol.71, no.4, pp.214-221, 2006 (Journal Indexed in SCI) identifier identifier

  • Publication Type: Article / Article
  • Volume: 71 Issue: 4
  • Publication Date: 2006
  • Doi Number: 10.3139/124.100296
  • Title of Journal : KERNTECHNIK
  • Page Numbers: pp.214-221

Abstract

Spent nuclear fuel resulting from reactor operation must be safely stored and managed prior to reprocessing and/or final disposal of high-level waste. Any spent fuel storage system must provide for safe receipt, handling, retrieval, and storage of spent fuel. In order to achieve the safe storage, the design should primarily provide for radiation protection, subcriticality of spent fuel, and removal of spent fuel residual heat. This article is focused on the design of a metal-shielded dry-cask storage system, which will host spent LWR fuels burned to 33 000, 45 000, and 55 000 MWd/t U and cooled for 5 or 10 years after discharge from reactor. The storage system is analyzed by taking into account radiation protection, subcriticality, and heat-removal aspects; and appropriate designs, in accordance with the international standards.