A behavior of O/M ratio and its effect for material accounting in high plutonium concentration MOX fabrication process
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works
Description
An evaluation test to investigate the behavior of the Oxygen to Metal ratio (hereinafter refer to O/M ratio) drift and its effect to material accounting in high plutonium concentration MOX fuel fabrication process was carried out in operational MOX fuel fabrication process of FBR line, Plutonium Fuel Production Facility (hereinafter refer to PFPF), Power Reactor and Nuclear Fuel Development Corporation (PNC). Because of the oxidation of uranium by the decay heat from plutonium in MOX, the O/M ratio may drift in powder treatment processes, and this may affect plutonium concentration of MOX, which is fundamental parameter of material control in MOX fabrication facility. To understand the behavior of O/M ratio, therefore, is important for material accounting in MOX facility. Also, if a non-uniform distribution of O/M ratio exists within a container accommodating feed powder or interim product of in-process, sample taking procedure should be established in such a way to obtain representative sample. Based on those consideration, the test was carried out in 1995 with PFPF. Gained experience with the improvement for material accounting system is discussed in this paper. (author)
Additional details
Additional titles
- Original title (English)
- Dai-17-kai kakubusshitsu kanri gakkai nippon shibu nenji taikai ronbunshu.
Publishing Information
- Publisher
- Nuclear Material Control Center.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the 17th annual meeting of INMM Japan Chapter
- Imprint Pagination
- 221 p.
- Journal Page Range
- p. 83-88.
Conference
- Title
- 17. annual meeting of INMM Japan Chapter.
- Dates
- 15-16 Oct 1996.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28059714
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCOUNTING; AFTER-HEAT; FUEL PELLETS; MIXED OXIDE FUELS; MONJU REACTOR; OXIDATION; PLUTONIUM; PLUTONIUM OXIDES; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; BREEDER REACTORS; CHALCOGENIDES; CHEMICAL REACTIONS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SODIUM COOLED REACTORS; SOLID FUELS; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS
Optional Information
- Notes
- Imprint:Dai-17-kai kakubusshitsu kanri gakkai nippon shibu nenji taikai ronbunshu.