Generation and validation of a cross section library based on ENDF/B-VI for the AUS neutronics code system.

dc.contributor.authorRobinson, GSen_AU
dc.date.accessioned2007-11-22T04:23:24Zen_AU
dc.date.accessioned2010-04-30T04:35:15Zen_AU
dc.date.available2007-11-22T04:23:24Zen_AU
dc.date.available2010-04-30T04:35:15Zen_AU
dc.date.issued1993-12en_AU
dc.description.abstractThe generation of a cross section library with 200 neutron and 37 photon groups from ENDF/B-VI for use in the AUS modular neutronics code system is described. The NJOY code was used for most of the library preparation but a revision of previous AUS methods was used for the neutron resonance treatment. The library should be suitable for thermal and fast fission reactors fusion blankets and various neutron applications. The validity of AUS with the library was established for thermal and fast reactor systems by an extensive set of comparisons with benchmark experiments which were mainly taken from the ENDF compilation. The performance of AUS with the library was much improved over that with the previous ENDF/B-IV based library.en_AU
dc.identifier.citationRobinson, G. S. (1993). Generation and validation of a cross section library based on ENDF/B-VI for the AUS neutronics code system. Lucas Heights, NSW: Australian Nuclear Science and Technology Organisation.en_AU
dc.identifier.govdoc500en_AU
dc.identifier.isbn0642599505en_AU
dc.identifier.issn10307745en_AU
dc.identifier.otherANSTO-E-712en_AU
dc.identifier.placeofpublicationLucas Heights, New South Walesen_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/490en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Nuclear Science and Technology Organisationen_AU
dc.subjectCross sectionsen_AU
dc.subjectThermonuclear reactorsen_AU
dc.subjectComputer calculationsen_AU
dc.subjectNuclear reactionsen_AU
dc.titleGeneration and validation of a cross section library based on ENDF/B-VI for the AUS neutronics code system.en_AU
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