3132

2917

كارشناسي ارشد

فيزيك

اصفهان: دانشگاه صنعتي اصفهان، دانشكده فيزيك

1384

هفت، 71،[II] ص.: مصور، جدول، نمودار.

1396/10/27

كتابنامه

فيزيك

فيزيك

ID2917

به فارسي و انگليسي: قابل رويت در نسخه ديجيتالي

AbstractBecause of the importance of security in designing and making nuclear reactors nuclear data which are used in neutronic reactors planning must have good accuracy So examination and welfare of nuclear data are in attention The aim of this thesis isinvestigation of neutron cross section with carbon and lead and conclusivelyimproving them We used blocks of lead and graphite in the Isfahan Center ofProduction and Research of Nuclear Fuel In the interior of lead carbon we place anAm Be source and then empirically measure flux of neutron outside The fluxdistribution is calculated theoretically by MCNP code and is compared withexperimental one Finally with the help of sensitivity coefficients definition the crosssection amounts are improved By more possibilities for fast neutron detection we canfind better results in other energy groups

اكبر پروازيان

احمد شيراني

حسين فقيهيان، محمدحسن علامت ساز