Published November 2005 | Version v1
Miscellaneous

Preliminary risk assessments for on-site spent nuclear fuel transportation Kori- site

  • 1. KAIST, Daejeon (Korea, Republic of)
  • 2. Nuclear Environment Technology Institute, Daejeon (Korea, Republic of)

Description

In this work, the risk due to the on-site transportation of spent nuclear fuel (SNF) in Kori-site is analyzed and then assessed with RADTRAN 5.5 code package. Many of specific data to Kori-site were used for the risk assessment even though some conservative input data were assumed and then used in case where there is no site-specific data available. The results of the risk assessments show that the radiation dose due to the Kori-site SNF transportation is much lower than the dose limits required by regulatory standards. In addition, this study shows that RADTRAN 5.5 code package had applicability to risk assessments of SNF on-site transportation

Part of:
Proceedings of international symposium on radiation safety management

Additional details

Publishing Information

Publisher
KHNP-KRWS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of international symposium on radiation safety management
Imprint Pagination
532 p.
Journal Page Range
p. 493-497

Conference

Title
2005 International Symposium on Radiation Safety Management
Dates
2-4 Nov 2005
Place
Daejeon (Korea, Republic of)

Optional Information

Notes
6 refs, 6 tabs