Published October 2017 | Version v1
Miscellaneous

Evaluation of Blast Wave Effects on Reactor Coolant System

  • 1. KEPCO E and C, Daejeon (Korea, Republic of)

Description

When a high energy line pipe break (HELB) occurs, the reactor coolant system (RCS) is affected by several dynamic effects. The effects of jet impingement, thrust, subcompartment pressurization, nozzle loads, and blowdown load in the reactor internals (RI) are generally known and have been evaluated so far. The RCS BLPB analyses for APR1400 had been performed for the break cases considering the dynamic effects except blast wave due to the HELB. Responses from the enveloped values of all break cases were used for the RCS design. In this study, the blast wave effects on the RCS due to the main steam nozzle break for APR1400 are evaluated. The forces and moments and response spectra induced by blast wave loads at the RCS main components are included in this evaluation. The structural analysis was performed to evaluate the blast wave effect on the RCS. The analysis results show that blast wave loads affect the responses in main steam nozzle break case. The supports and nozzle loads of the RCS and the response spectra of the SG are increased. However, the supports and nozzle loads are enveloped by other break cases and only high frequency regions of the response spectra are affected.

Part of:
Proceedings of the KNS 2017 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2017 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[4 p.]

Conference

Title
2017 Fall Meeting of the KNS
Dates
25-27 Oct 2017
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49078827
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BLOWDOWN; DESIGN; DYNAMICS; LEAKS; NOZZLES; PRESSURIZATION; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; STEAM GENERATORS; USES
Descriptors DEC
BOILERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 2 figs, 13 tabs