5317

4987

كارشناسي ارشد

فيزيك

اصفهان: دانشگاه صنعتي اصفهان، دانشكده فيزيك

1388

ده،77ص.:مصور﴿بخش رنگي﴾،جدول،نمودار

ص.ع.به فارسي و انگليسي

احمد شيراني

ايرج شهابي

13/4/89

فيزيك

ID4987

به فارسي و انگليسي: قابل رويت در نسخه ديجيتالي

Investigation of reactivity changes due to flooding of the MNSR inner irradiation sites using the MCNP code and comparison with experimental results Hadi Shamoradi far h shamoradifar@ph iut ac ir 3 March 2010 Department Of Physics Isfahan University of Technology Isfahan 84156 83111 Iran Degree M Sc Language Farsi Ahmad Shirani Shirani@cc iut ac ir Abstract The miniature Neutron Source Reactor MNSR is manufactured by the Chinese Institute of Atomic Energy It is a low power tank in pool type research reactor and similar to the Canadian SLOWPOKE Reactor The reactor employs highly enriched uranium as fule 90 2 light water as moderator and coolant and metal beryllium as reflector Heat generated in the core is removed through natural convection In this work the Isfahan Miniature Neutron Source Reactor MNSR has been simulated using the MCNP Code and reactivity worth of flooding the inner irradiation sites of this reactor in an accident hasbeen calculated Also by putting polyetilen capsuls containing water inside the inner irradiation sites reactivity changes of this reactor in such an accident have been measured the results of which are in good agreements with the calculated results In this work the reactivity worth due to flooding one inner irradiation site is about 0 53 mk and reactivity worth due to flooding of the whole 5 inner irradiation sites is estimated to be about 2 5 mk Key words MCNP Code Monte Carlo Simulation Reactivity MNSR Reactor

احمد شيراني

ايرج شهابي