کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
8068373 | 1521115 | 2015 | 7 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Minimizing MTR reactor uranium load with the use of MOX fuel by employing ORIGEN-S and MCNP4C codes
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
![عکس صفحه اول مقاله: Minimizing MTR reactor uranium load with the use of MOX fuel by employing ORIGEN-S and MCNP4C codes Minimizing MTR reactor uranium load with the use of MOX fuel by employing ORIGEN-S and MCNP4C codes](/preview/png/8068373.png)
چکیده انگلیسی
A computational study was performed for MTR reactors using ORIGEN-S and MCNP4C codes to replace some of the fuel elements (FEs) with MOX FEs. The results show that the replacement of the MTR-22Â MW power research reactor Fes with MOX FEs leads to the reduction in the enrichment with 235U and the amount of loaded 235U in the core up to more than 20%. The amount of loaded uranium 235U FEs decreased considerably by increasing the number of MOX FEs. Re-evaluated neutronic parameters of the reactor showed that the replacement of the FEs by MOX FEs does not affect negatively the safe operational conditions of the reactor with practically no harmful effect on the safety of the reactor.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 83, September 2015, Pages 34-40
Journal: Annals of Nuclear Energy - Volume 83, September 2015, Pages 34-40
نویسندگان
Ismail Shaaban, Mohamad Albarhoum,