Published May 2018 | Version v1
Miscellaneous

Simulation Study of Total Loss of Feedwater in OPR1000 using SPACE

  • 1. Korea Hydro and Nuclear Power Central Research Institute, Daejeon (Korea, Republic of)
  • 2. System Engineering and Technology Co. Ltd., Daejeon (Korea, Republic of)

Description

Additional failure of the safety components are also considered in terms of sufficient safety margin with application of proper emergency operating procedures. In this paper, we studied about Total Loss of Feedwater (TLOFW) accident which is used to represent an accident involving the failure of cooling by the secondary cooling system. This work is focused on the thermal-hydraulic analysis for TLOFW accident in OPR1000 plant using Safety and Performance Analysis Code for Nuclear Power Plant (SPACE). Based on the thermal hydraulic features, simulation studies can provide physical insight to the system response and confirm the effectiveness of RCS cool down strategy according to the emergency operating guideline. In this study, the TLOFW accident in OPR1000 plant were assessed using SPACE 3.0. Two different cases were simulated to confirm safety criteria. In both cases, it is verified that the core cooling capability is sufficient. In case 2, it is expected that fuel rod is heated up in a short time.

Part of:
Proceedings of the KNS 2018 Spring Meeting

Additional details

Identifiers

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2018 Spring Meeting
Imprint Pagination
vp.
Journal Page Range
[3 p.]

Conference

Title
2018 Spring Meeting of the KNS
Dates
16-18 May 2018
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50059445
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; FAILURES; FEEDWATER; PERFORMANCE; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; S CODES; SAFETY; VERIFICATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 9 figs, 2 tabs