Preliminary neutronic study of the S-PRISM fast reactor
نویسندگان
چکیده
Waste management is a challenge currently faced by nuclear energy worldwide. Most power plants operate in once-through cycle and all spent fuel stored long term. Fast reactors can recycle 96% of the material thermal reactors, reducing drastically time required to store waste. The S-PRISM reactor modular, pool-type sodium-cooled fast that with variety types. In this study, advantages presented were briefly discussed preliminary analysis pin cells was made. It found isothermal coefficient reactivity lower than regular PWR's, neutron leakage playing major role instead coolant or doppler expansion. k? showed decrease for driver increase blanket during burnup; opposite behavior observed conversion ratio. No results literature comparison. As simulations carried out separately system, are not representative whole core but must be seen as path understand different types influence system.
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ژورنال
عنوان ژورنال: Brazilian Journal of Radiation Sciences
سال: 2021
ISSN: ['2319-0612']
DOI: https://doi.org/10.15392/bjrs.v8i3a.1580