Safety Function Evaluation for the Decay Heat Removal System of a Sodium Cooled Fast Reactor
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Korea Atomic Energy Research Institute (KAERI) has been developing an advanced sodium-cooled fast reactor (SFR) that meets the design goals of GEN IV reactors. The sodium-cooled fast reactor is the pool type sodium cooled fast reactor with the thermal power of 1548.2 MW and the core loaded with metal fuel, which is consists of primary heat transport system, intermediate heat transport system, steam generating System, and decay heat removal system. The decay heat removal system is composed of 2 units of passive decay-heat removal circuits (PDRC) and 2 units of active decay-heat removal circuits (ADRC) considering 200% heat removal capacity. Decay heat removal system removed the decay heat produced in the core during planned and unplanned shutdown of the reactor to respect design limits. For the safety function evaluation for the decay heat removal system, the 4 DBE's(Design Bases Events) are analyzed using MARS-LMR
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
- 2011 autumn meeting of the KNS
- Dates
- 26-28 Oct 2011
- Place
- Kyoungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 43045264
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; DESIGN; SAFETY; SODIUM COOLED REACTORS; STEAM GENERATORS
- Descriptors DEC
- BOILERS; LIQUID METAL COOLED REACTORS; REACTORS; REMOVAL; VAPOR GENERATORS
Optional Information
- Notes
- 2 refs, 6 figs, 1 tab