Decay Heat Analysis of a TRU-fueled Deep Burn VHTR Core
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The decay heat of radioactive isotopes is one of main concerns in designing a reactor core as well as designing a spent fuel repository. In particular, the effective removal of the decay heat during accidents such as high or low pressure conduction cooling events is a crucial factor which determines the main design parameters of a very high temperature gas cooled reactor (VHTR) core. In our previous work, a sophisticated decay heat analysis procedure by using McCARD code and ORIGEN-2 code was introduced and a decay heat analysis of PMR200, a uranium-fueled VHTR, core was demonstrated. In this study, the decay heat of a TRU-fueled deep burn VHTR core was analyzed by using the McCARD/ORIGEN-2 procedure introduced in reference 1
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2009 autumn meeting of the KNS
- Dates
- 29-30 Oct 2009
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 41027134
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT; BURNS; DESIGN; M CODES; O CODES; REACTOR CORES; SPENT FUELS; VHTR REACTOR
- Descriptors DEC
- COMPUTER CODES; DISEASES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INJURIES; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 7 refs, 5 figs, 2 tabs