Published May 1998 | Version v1
Miscellaneous

Analysis of the nuclear subcriticality for the high density spent fuel storage at PWR plants

  • 1. NETEC, Taejon (Korea, Republic of)
  • 2. KAIST, Taejon (Korea, Republic of)

Description

The marginal nuclear criticality analysis for the high density spent fuel storage at a PWR plant was carried out by using the HELIOS and CASMO-3 codes. More than 20 % of the calculated reactivity saving effect is observed in this analysis. This mainly comes from the adoption of some important fission products and B-10 in the criticality analysis. By taking burnup and boron credits, the high capacity of the spent fuel storage rack can be more fully utilized, reducing the space of storage. Larger storage for a given inventory of spent fuel should result in remarkable cost savings and more importantly reduce the risks to the public and occupational workers

Part of:
Proceedings of the Korean Nuclear Society spring meeting Vol. 2

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting Vol. 2
Imprint Pagination
1031 p.
Journal Page Range
p. 470-475

Conference

Title
1998 spring meeting of the Korean Nuclear Society
Dates
29-30 May 1998
Place
Seoul (Korea, Republic of)

Optional Information

Notes
3 refs, 4 figs, 2 tabs