Sensitivity analyses on hydrogen generation for KNGR using MELCOR
- 1. KAERI, Taejon (Korea, Republic of)
Description
The amount of in-vessel hydrogen generation during severe accidents affects the integrity of containment. For the Korean Next Generation Reactors, sensitivity analyses on the in-vessel hydrogen generation are described. The typical accident sequences of a station blackout and a large LOCA scenario are selected. A lower head failure model, a Zircaloy oxidation reaction model and a B4C oxidation reaction model are considered as the sensitivity parameters. As for the base case, 1273.15K for a failure temperature of the penetrations or the lower head, an Urbanic-Heidrich correlation for the Zircaloy oxidation reaction model and the B4C oxidation reaction model are used. The results of the studies are summarized below : (1) When the penetration failure temperature is higher, or the creep rupture failure model is considered, the amount of hydrogen increases for two sequences. (2) When the MATPRO-EG and G correlation for a Zircaloy oxidation reactor is considered, the amount of hydrogen is less than the Urbanic-Heidrich correlation (Base cae) for both scenarios. (3) When the B4C reaction model turns off, the amout of hydrogen decreases for two sequences
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society spring meeting
- Imprint Pagination
- [ONE CDROM]
- Journal Page Range
- [13 p.]
Conference
- Title
- 2001 spring meeting of the Korean Nuclear Society
- Dates
- 24-25 May 2001
- Place
- Cheju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33040426
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONTAINMENT; INTERSTITIAL HYDROGEN GENERATION; M CODES; OXIDATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; SENSITIVITY ANALYSIS; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; COMPUTER CODES; ENRICHED URANIUM REACTORS; PHYSICAL RADIATION EFFECTS; POWER REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 8 refs, 6 figs, 4 tabs