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)
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.