Published 1988 | Version v1
Report Restricted

Verification of the OREST (HAMMER-ORIGEN) depletion program system using post-irradiation analyses of fuel assemblies 168, 170, 171 and 176 from the Obrigheim Reactor

Creators

Description

Recycling calculations for UO2 and mixed oxide (MOX) fuel are being carried out in conjunction with project SR 316 entitled ''Safety Analysis for Thermal Recycling in the Federal Republic of Germany.'' On the basis of the calculated nuclide inventories in spent fuel assemblies it is then possible to treat safety issues related to thermal recycling. The reliable determination of fission material quantities and their composition is therefore of particular importance. The OREST program system is used to calculate the nuclide inventories in spent UO2 and MOX fuel assemblies. In this report the reliability of the OREST system for UO2 burnup in pressurized water reactors is first demonstrated. Post-irradiation analyses of five UO2 fuel assemblies from the Obrigheim Pressurized Water Reactor (KWO) with an initial enrichment of 3.13 wt% U-235 and a mean burnup rate of 28.4 GWd/tU are used as a yardstick

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 as DE88017045.

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Additional details

Publishing Information

Imprint Pagination
32 p.
Report number
ORNL/tr--88/20

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20011055
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Translation
Descriptors DEI
FEDERAL REPUBLIC OF GERMANY; H CODES; MIXED OXIDE FUELS; NEUTRON SPECTRA; O CODES; PLUTONIUM; POST-IRRADIATION EXAMINATION; PWR TYPE REACTORS; RADIOISOTOPES; REPROCESSING; SAFETY; SPENT FUEL ELEMENTS; URANIUM DIOXIDE; URANIUM 235
Descriptors DEC
ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; COMPUTER CODES; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EUROPE; EVEN-ODD NUCLEI; FUEL ELEMENTS; FUELS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTO; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FUELS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SOLID FUELS; SPECTRA; SPONTANEOUS FISSION RADIOISOTO; THERMAL REACTORS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
Translation of GRS-A-962, May 1984, pp. 1-32 Portions of this document are illegible in microfiche products.