Enhancing MA transmutation by irradiation of (MA, Zr)Hx in FBR blanket region - 5383
- 1. Institute for Materials Research, Tohoku University, Oarai, Ibaraki-ken, 311-1313 (Japan)
- 2. Mitsubishi FBR Systems, Inc., 34-17, Jingumae 2-Chome, Shibuya-ku, Tokyo 150-0001 (Japan)
- 3. Nuclear Development Corporation, 622-12, Funaishikawa, Tokaimura, Ibaraki 319-1111 (Japan)
- 4. Nippon Nuclear Fuel Development Co. Ltd., Oarai, Ibaraki-ken, 311-1313 (Japan)
- 5. Central Research Institute of Electric Power Industry, Komae, Tokyo 201-8511 (Japan)
- 6. Division of Sustainable Energy and Environmental Engineering, Graduate School of Engineering, Osaka University, 2-1 Yamadaoka, Suita-shi, Osaka 565-0871 (Japan)
Description
Minor actinide (MA) hydride is proposed as transmutation target in sodium-cooled mixed oxide fuelled fast reactor. Preliminarily calculations have been done to check the transmutation efficiency of MA hydride targets. Three different types of MA target, MA-Zr alloy, (MA, Zr)O2 and (MA, Zr)Hx, have been compared on MA transmutation rate. The targets are assumed to be loaded around an active core in a 280 MWe sodium-cooled reactor; 54 MA target assemblies are respectively arranged in a row in the radial blanket zone. They are supposed to be irradiated for one year and then be cooled for 60 days. The transmuted mass has been evaluated by three-dimensional diffusion calculation to be 25, 15, 61 kg/EFPY for the alloy, the oxide and the hydride respectively, where production of MA in the active core is taken into account. The transmutation mass by (MA, Zr)Hx is much larger than those by the other types of targets, while the core characteristics remain sound by locating MA targets outside of the active core. On top of that, two kinds of (MA, Zr)O2 targets which are combined with ZrHx(x=1.7) pins have been calculated. Major Research/Development items are selected to establish the MA hydride transmutation method by reviewing technologies applicable to the transmutation system. The practical use of the MA hydride transmutation method is not far ahead technically, since this method can be developed by the extension of existing technologies. (authors)
Availability note (English)
Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France)Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- ISBN
- 978-1-4951-6286-2
- Imprint Title
- GLOBAL 2015 Proceedings
- Imprint Pagination
- 2455 p.
- Journal Page Range
- p. 615-624
Conference
- Title
- Nuclear fuel cycle for a low-carbon future
- Acronym
- GLOBAL 2015
- Dates
- 21-24 Sep 2015
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49023726
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDE BURNER REACTORS; COMPUTERIZED SIMULATION; CONVERSION RATIO; HYDRIDES; POST-IRRADIATION EXAMINATION; SODIUM COOLED REACTORS; TARGETS; TRANSMUTATION; VALIDATION
- Descriptors DEC
- DIMENSIONLESS NUMBERS; EPITHERMAL REACTORS; FAST REACTORS; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; REACTORS; SIMULATION; TESTING
Optional Information
- Notes
- 28 refs.