Published October 2012 | Version v1
Miscellaneous Metadata-only

Evaluation of SPACE code for simulation of reactor scram due to unplanned loss of RCP power in OPR 1000

Creators

  • 1. KHNP Central Research Institute, Daejeon (Korea, Republic of)

Description

SPACE (Safety and Performance Analysis Code for Nuclear Power Plants) has been developing by KHNP with the cooperation with KEPCO E and C and KAERI. SPACE code is expected to be applied to the safety analysis for LOCA (Loss of Coolant Accident) and Non LOCA scenarios. SPACE code solves two fluid, three field governing equations and programmed with C++ computer language using object oriented concepts. To evaluate the analysis capability for the transient phenomena in the actual nuclear power plant, the reactor trip accident due to the loss of RCP power in OPR1000 (Ulchin unit 4) was simulated with SPACE code

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2012 autumn meeting of the KNS
Dates
24-26 Oct 2012
Place
Kyoungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44062790
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; LOSS OF COOLANT; PWR TYPE REACTORS; S CODES; SAFETY ANALYSIS; SCRAM
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs, 5 figs, 2 tab