Published October 2015 | Version v1
Miscellaneous

Sensitivity studies for 3-D rod ejection analyses on axial power shape

  • 1. KEPCO NF, Daejeon (Korea, Republic of)

Description

The current safety analysis methodology using the point kinetics model combined with numerous conservative assumptions result in unrealistic prediction of the transient behavior wasting huge margin for safety analyses while the safety regulation criteria for the reactivity initiated accident are going strict. To deal with this, KNF is developing a 3-D rod ejection analysis methodology using the multi-dimensional code coupling system CHASER. The CHASER system couples three-dimensional core neutron kinetics code ASTRA, sub-channel analysis code THALES, and fuel performance analysis code FROST using message passing interface (MPI). A sensitivity study for 3-D rod ejection analysis on axial power shape (APS) is carried out to survey the tendency of safety parameters by power distributions and to build up a realistic safety analysis methodology while maintaining conservatism. The currently developing 3-D rod ejection analysis methodology using the multi-dimensional core transient analysis code system, CHASER was shown to reasonably reflect the conservative assumptions by tuning up kinetic parameters

Part of:
Proceedings of the KNS 2015 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2015 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2015 Fall meeting of the KNS
Dates
28-30 Oct 2015
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47085231
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONTROL ELEMENTS; DOPPLER EFFECT; F CODES; FAILURES; NUCLEAR POWER PLANTS; PERFORMANCE TESTING; POWER DISTRIBUTION; REACTIVITY; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; TRANSIENTS
Descriptors DEC
COMPUTER CODES; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; TESTING; THERMAL POWER PLANTS

Optional Information

Notes
2 refs, 8 figs, 2 tabs