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Title: ANL pre analysis of the SHEBA/CERES experiments.

Abstract

The French and British nuclear programs have prepared a series of natural uranium oxide fuel samples spiked with small amounts of the individual fission products which makeup a large fraction of the total neutron absorption by fission products in spent nuclear fuel. Both programs have utilized these samples in experimental reactors and have inferred the worth of the individual fission products. These results have been used to validate the cross sections used in criticality safety calculations. These measurements constitute a major element in support of spent fuel burnup credit in these countries.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab., IL (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
757501
Report Number(s):
ANL-FRA-2000-1
TRN: US0100308
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 5 May 2000
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ANL; CROSS SECTIONS; EXPERIMENTAL REACTORS; FISSION PRODUCTS; NATURAL URANIUM; NUCLEAR FUELS; SPENT FUELS

Citation Formats

Palmiotti, G., Smith, M., Klann, R., Fujita, E., and Imel, G. ANL pre analysis of the SHEBA/CERES experiments.. United States: N. p., 2000. Web. doi:10.2172/757501.
Palmiotti, G., Smith, M., Klann, R., Fujita, E., & Imel, G. ANL pre analysis of the SHEBA/CERES experiments.. United States. doi:10.2172/757501.
Palmiotti, G., Smith, M., Klann, R., Fujita, E., and Imel, G. Fri . "ANL pre analysis of the SHEBA/CERES experiments.". United States. doi:10.2172/757501. https://www.osti.gov/servlets/purl/757501.
@article{osti_757501,
title = {ANL pre analysis of the SHEBA/CERES experiments.},
author = {Palmiotti, G. and Smith, M. and Klann, R. and Fujita, E. and Imel, G.},
abstractNote = {The French and British nuclear programs have prepared a series of natural uranium oxide fuel samples spiked with small amounts of the individual fission products which makeup a large fraction of the total neutron absorption by fission products in spent nuclear fuel. Both programs have utilized these samples in experimental reactors and have inferred the worth of the individual fission products. These results have been used to validate the cross sections used in criticality safety calculations. These measurements constitute a major element in support of spent fuel burnup credit in these countries.},
doi = {10.2172/757501},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {5}
}