Published 2007 | Version v1
Miscellaneous

Re-evaluation of NUPEC M-7-1 Hydrogen Experiment using MELCOR 1.8.6

  • 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

Evaluation of hydrogen distribution in containment building is still of keen interests. KINS is evaluating the hydrogen risk for the continued operation of Kori-1 and also for the new reactors like Shin-Kori-1,2, Shin Wolsong-1,2 etc. Considering these needs and also that the code used in KINS is moving from MELCOR 1.8.5 to MELCOR 1.8.6, we have evaluated the NUPEC hydrogen test M-7-1 using MELCOR 1.8.6. The NUPEC test was chosen just because it is the only available data we have. We will continue to evaluate other experimental data of hydrogen once they are available. In NUPEC's Hydrogen Mixing and Distribution Test M-7-1, steam/helium mixture was released into the lower region of a simplified 1/4 scale model of large dry containment of 4-loop PWR(fig.1) to simulate break of a steam generator (SG) system. Total helium volume was decided by volumetric scaling of hydrogen released due to 100% Zr-H2O reaction. At the same time, containment spray was also activated to simulate the impact of spray water. Test containment had 25 compartments and 66 paths, and each compartment had measuring instruments for temperature (wall/air), pressure and helium concentration

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2007 spring meeting of the KNS
Dates
10-11 May 2007
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38113492
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; CONTAINMENT MOCKUP FACILITY; HYDROGEN; M CODES; PWR TYPE REACTORS; STEAM GENERATORS
Descriptors DEC
BOILERS; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; HEAVY WATER MODERATED REACTORS; NONMETALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR SAFETY EXPERIMENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 6 figs