System Configuration of a SFR Demonstration Plant Developing in KAERI
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The one of long-term R and D plans aims to build an advanced SFR (Sodium-cooled Fast Reactor) demonstration plant by 2028. Currently a conceptual design phase (2007∼2011) is in progress. The goals of the plant are to verify a transuranics (TRU) burning function and several technical issues. This paper describes what's different in SFR compared to PWR (Pressurized Water Reactor). The NSSS (Nuclear Steam Supply System) of a SFR has several different design features compared to a PWR because of the use of liquid metal sodium at high temperature environment instead of the use of water as coolant. The sodium coolant is under atmospheric pressure, and the operating temperature is around 500 .deg. C. Unlike a PWR, the fuel exchange should be performed in the inert gas environment without opening the reactor head
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
- 43045308
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN; KAERI; PWR TYPE REACTORS; SODIUM COOLED REACTORS; STEAM SYSTEMS
- Descriptors DEC
- ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; KOREAN ORGANIZATIONS; LIQUID METAL COOLED REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 ref, 2 figs