Use of Void Duct Assemblies for TRU Transmutation Core Design
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
It has been well-known that the radiotoxicity of the long-lived nuclides (e.g., Pu, Np, Am, Cm, 129I, 99Tc) contained in LWR spent fuel lasts over very long time period. Therefore, many countries have launched their own national program and have participated international collaborative projects (e.g., Gen-IV) to investigate the possibility of reduction of these nuclides by the nuclear transmutation. In this paper, a new design concept for the effective transmutation of transuranics (TRU) (i.e., Pu, Am, Cm, Np) nuclides is presented. In this core design concept, the void duct assemblies are used to reduce the coolant void reactivity that is one of the technical issues related with core safety and to achieve power flattening under single enrichment fuel
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2005 autumn meeting of the KNS
- Dates
- 27-28 Oct 2005
- Place
- Busan (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37071988
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN; DUCTS; SAFETY; SPENT FUELS; TRANSMUTATION; VOIDS; WATER COOLED REACTORS
- Descriptors DEC
- ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS
Optional Information
- Notes
- 4 refs, 1 fig, 2 tabs