Published May 2001 | Version v1
Miscellaneous

A computer code development for evaluation of primary coolant specific activities using ORIGEN2 code

  • 1. Seoul National Univ., Seoul (Korea, Republic of)
  • 2. KAERI, Taejon (Korea, Republic of)

Description

A computer program SAEP to evaluate specific activities due to fission products in the primary coolant was developed, which can be applied to the integral reactor such as SMART as well as commerical PWRs in existence. The ORIGEN2 code is integrated into the SAEP as a subroutine, which could solve the inhomogeneous differential equations to detemine coolant activities, The benchmarking result for UCN 3 and 4 units shows that specific activities by the SAEP are very close to those of the conventional calculations. Terefore, it is expected that the SAEP developed in this study will be used practically in evaluation of specific activities in the primary coolant of various types of nuclear reactors including the integral reactor

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[12 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Optional Information

Notes
6 refs, 3 tabs