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Neutronic analysis of (ThO2-EnrichedUO2) replacement with natUO2 fuel in a typical heavy water research reactor | ||
| Iranian Journal of Science | ||
| مقالات آماده انتشار، پذیرفته شده، انتشار آنلاین از تاریخ 11 تیر 1395 | ||
| نوع مقاله: Regular Paper | ||
| شناسه دیجیتال (DOI): 10.22099/ijsts.2016.3753 | ||
| نویسندگان | ||
| Masoomeh Alizadeh Kavafshary1؛ Seyed Mohammad Mirvakili1؛ atieh Joze Vaziri* 2؛ Zohreh Gholamzadeh1 | ||
| 1AEOI | ||
| 2atomic energy organization of Iran | ||
| چکیده | ||
| Theoretical and experimental investigations reveal that thorium-based fuel could potentially be a proper alternative in nuclear fuel cycle technology. Hence, the neutronic performance of an enriched uranium/thorium oxide fuel loading in a typical heavy water research reactor is computationally evaluated in the present study. The obtained data shows that the thorium-based fuel has a less negative temperature coefficient in comparison with the natUO2 fuel loading. Meantime, the thorium-based fuel loading in the typical core configuration did not drastically reduce the β parameter. Rather higher conversion factor and less transuranic production of the thorium-based fuel cycle makes it favorable either to achieve higher cycle length or less dangerous and costly waste disposal. | ||
| کلیدواژهها | ||
| Neutronic investigation؛ natUO2؛ (ThO2/EnrichedUO2)؛ MCNPX 2.6.0؛ burn-up | ||
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آمار تعداد مشاهده مقاله: 733 |
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