Published 2004 | Version v1
Miscellaneous

Analysis of radiation field distribution in Yonggwang unit 3 with MCNP code

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

Radiation field analysis is performed at the inside of the containment building of nuclear power plant(NPP) using the well-known MCNP code. The target NPP in this study is Yonggwang Unit 3 Cycle 8. In this work, whole transport calculations were done using MCNPX 2.4.0 due to the functional benefits, such as Mesh Tally, that the code provides. The neutron spectra released from the operating reactor core were firstly evaluated as a radiation source term, and then dose distributions in the work areas of the NPP were calculated

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
1466 p.
Journal Page Range
p. 1107-1108

Conference

Title
2004 autumn meeting of the KNS
Dates
28-29 Oct 2004
Place
Yongpyong (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36102576
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; CONTAINMENT BUILDINGS; M CODES; NEUTRON SPECTRA; RADIATION DOSE DISTRIBUTIONS; REACTOR CORES; REACTOR OPERATION; SOURCE TERMS; YONGGWANG-3 REACTOR
Descriptors DEC
BUILDINGS; COMPUTER CODES; CONTAINMENT; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SPECTRA; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref, 4 figs