Abstract
Calculations are made to investigate sensitivities of the central NISUS spectrum and reaction-rate ratios to uncertainties in the macroscopic configuration. These uncertainties include density (of graphite, borone carbide and natural uranium), impurity (moisture and 10B in graphite), abundance ( 10B natural abundance) and tolerance (in Al cladding and B 4C shell). The sensitivities to the variations in the fission cross section of 235U and 238U are also studied. In these calculations the ANISN one-dimensional transport code is used with a 37 group data set derived from the UKAEA Nuclear Data Library by the GALAXY processing code. The effects of uncertainties are studied in detail and a comparison is made between the NISUS and MOL-ΣΣ standard neutron fields.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
