Current activities in criticality analyses for final disposal of spent nuclear fuel and fissile material containing waste in Germany
- 1. Gesellschaft fuer Anlagen und Reaktorsicherheit, Garching (Germany)
- 2. Bundesamt fuer Strahlenschutz, Salzgitter (Germany)
Description
This paper gives a short overview on the work which was done recently or is underway for criticality safety analyses for final disposal of fissile material containing waste and spent nuclear fuel in Germany. For Plutonium containing low-level waste a modification of criticality safety limits is proposed, taking into account the fractions of Pufiss and 240Pu. For final disposal of spent nuclear fuel studies on long term sub-criticality are being performed with the aim of comparing different host rock materials. The paper reports on first results of generic criticality analyses for a clay formation. The analyses are based on long term scenarios, which were proposed by experts in geo-chemistry, dealing with long term problems in disposal research. (author)
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Additional details
Publishing Information
- Imprint Title
- ICNC2003: Proceedings of the seventh international conference on nuclear criticality safety. Challenges in the pursuit of global nuclear criticality safety
- Imprint Pagination
- 466 p.
- Journal Page Range
- p. 389-394
- Report number
- JAERI-Conf--2003-019-PT1
Conference
- Title
- 7. international conference on nuclear criticality safety. Challenges in the pursuit of global nuclear criticality safety
- Acronym
- ICNC2003
- Dates
- 20-24 Oct 2003
- Place
- Tokai, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36116487
- Subject category
- S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMERICIUM 241; BWR TYPE REACTORS; CRITICALITY; FEDERAL REPUBLIC OF GERMANY; FISSILE MATERIALS; GEOCHEMISTRY; MIXED OXIDE FUELS; PLUTONIUM; PLUTONIUM 239; PLUTONIUM 240; PLUTONIUM 241; PWR TYPE REACTORS; RADIOACTIVE WASTE DISPOSAL; SPENT FUELS; STORAGE; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHALCOGENIDES; CHEMISTRY; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EUROPE; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FISSIONABLE MATERIALS; FUELS; HEAVY NUCLEI; ISOTOPES; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM ISOTOPES; POWER REACTORS; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS; URANIUM OXIDES; WASTE DISPOSAL; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 12 refs., 3 figs., 5 tabs.; This record replaces 35060862