Published 2003 | Version v1
Computer medium

Development of main steam line break mass and energy release analysis methodology with RETRAN-3D code

  • 1. Korea Electric Power Research Inst., Taejon (Korea, Republic of)

Description

The estimation methodology of the mass and energy (M/E) release in the main steam line break (MSLB) has been developed with the RETRAN-3D code. In the case of equipment qualification (EQ), the over-estimated temperature would exceed the design limits of some cables or valves. In order to have a more flexible EQ profiles from the MSLB M/E release, the methodology with the best-estimated code was used. The major conditions affecting the MSLB M/E were found to be the initial SG level, heat transfer between primary and secondary sides, power level, operable protection system, main or auxiliary feedwater availability, and break conditions. The RETRAN-3D models were developed for the Kori unit 1(KRN-1) which is typical two loop Westinghouse (WH) designed plant. Particularly, a detailed model of the steam generators was developed to estimate a more realistic two-phase heat transfer effect of the steam flow. After the modeling, the methodology has been developed through the sensitivity analyses. The M/E release data generated from the analyses have been used as the input to the inside containment pressure and temperature (P/T) analysis. According to the results at the point of view containment P/T, the Kori unit 1 can have more margin of 5 - 15 kPa in pressure and 8 - 15degC in temperature. (author)

Part of:
ICONE-11: Proceedings of the 11th international conference on nuclear engineering

Additional details

Publishing Information

Publisher
Japan Society of Mechanical Engineers
Imprint Place
Tokyo (Japan)
Imprint Title
ICONE-11: Proceedings of the 11th international conference on nuclear engineering
Imprint Pagination
[3610 p.]
Journal Page Range
[8 p.]

Conference

Title
11. international conference on nuclear engineering
Acronym
ICONE-11
Dates
20-23 Apr 2003
Place
Tokyo (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
35045114
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FEEDWATER; HYDRAULICS; LOSS OF COOLANT; PRESSURE DEPENDENCE; STEAM GENERATORS; STEAM LINES; TEMPERATURE DEPENDENCE; THERMODYNAMICS; TRANSIENTS
Descriptors DEC
ACCIDENTS; BOILERS; FLUID MECHANICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; PIPELINES; REACTOR ACCIDENTS; VAPOR GENERATORS; WATER

Optional Information

Notes
This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Track No. 05, Session 5-6, ICONE-36278; 9 refs., 21 figs.