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Alizadeh Kavafshary, Masoomeh, Mirvakili, Seyed Mohammad, Joze Vaziri, atieh, Gholamzadeh, Zohreh. (1395). Neutronic analysis of (ThO2-EnrichedUO2) replacement with natUO2 fuel in a typical heavy water research reactor. , (), -. doi: 10.22099/ijsts.2016.3753
Masoomeh Alizadeh Kavafshary; Seyed Mohammad Mirvakili; atieh Joze Vaziri; Zohreh Gholamzadeh. "Neutronic analysis of (ThO2-EnrichedUO2) replacement with natUO2 fuel in a typical heavy water research reactor". , , , 1395, -. doi: 10.22099/ijsts.2016.3753
Alizadeh Kavafshary, Masoomeh, Mirvakili, Seyed Mohammad, Joze Vaziri, atieh, Gholamzadeh, Zohreh. (1395). 'Neutronic analysis of (ThO2-EnrichedUO2) replacement with natUO2 fuel in a typical heavy water research reactor', , (), pp. -. doi: 10.22099/ijsts.2016.3753
Alizadeh Kavafshary, Masoomeh, Mirvakili, Seyed Mohammad, Joze Vaziri, atieh, Gholamzadeh, Zohreh. Neutronic analysis of (ThO2-EnrichedUO2) replacement with natUO2 fuel in a typical heavy water research reactor. , 1395; (): -. doi: 10.22099/ijsts.2016.3753

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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