Plutonium and minor actinides utilization in Thorium molten salt reactor

Waris, Abdul; Aji, Indarta Kuncoro; Novitrian, Novitrian; Kurniadi, Rizal; Su’ud, Zaki

doi:10.1063/1.4725445

Cited by 4 publications

(2 citation statements)

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“…This may due to the larger microscopic absorption crosssection of TRU, such as Pu-239 and Pu-241 in the thermal energy region. This fact has been reported in our previous study [9]. Moreover, the neutron spectra also become harder with the rising uranium enrichment in the loaded fresh fuel.…”

Section: Resultssupporting

confidence: 86%

Preliminary study on direct recycling of spent PWR fuel in PWR system

Waris¹,

Nuha²,

Novitrian³

et al. 2012

AIP Conference Proceedings

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Preliminary study on direct recycling of PWR spent fuel to support SUPEL (Straight Utilization of sPEnt LWR fuel in LWR system) scenario has been conducted. Several spent PWR fuel compositions in loaded PWR fuel has been evaluated to obtain the criticality of reactor. The reactor can achieve it criticality for U-235 enrichment in the loaded fresh fuel is at least 4.0 a% with the minimum fraction of the spent fuel in the core is 15.0 %. The neutron spectra become harder with the escalating of U-235 enrichment in the loaded fresh fuel as well as the amount of the spent fuel in the core.

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Section: Resultssupporting

confidence: 86%

Preliminary study on direct recycling of spent PWR fuel in PWR system

Waris¹,

Nuha²,

Novitrian³

et al. 2012

AIP Conference Proceedings

Self Cite

View full text Add to dashboard Cite

show abstract

“…This may due to the larger microscopic absorption cross-section of TRU, such as Pu-239 and Pu-241 in the thermal energy region. This fact has been reported in our previous study [8]. Moreover, the neutron spectra also become harder with the rising uranium enrichment in the loaded fresh fuel.…”

Section: Resultsmentioning

confidence: 61%

Preliminary study on direct recycling of spent BWR fuel in BWR system

Waris¹,

Sumbono²,

Prayudhatama³

et al. 2012

AIP Conference Proceedings

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Spent fuel management is considered to be one of the main problems in energy nuclear utilization. Recycling after reprocessing is one of the options for dealing with nuclear reactor spent fuel. Reprocessing is very costly and needs remote handling since spent fuel is very hazard high level waste. On top of that, only a small number of countries can manage a reprocessing plant. If country likes Indonesia decide to "go nuclear", it should find another way to deal with the nuclear spent fuel. Korea has proposed the DUPIC (Direct Utilization of Spent PWR fuel In CANDU) concept. Nevertheless, DUPIC concept requires two types of nuclear power plants, i.e., pressurized water reactor (PWR) and CANadian Deuterium Uranium reactor (CANDU). In this study, we evaluate a scheme of direct recycling of spent BWR fuel in BWR system, under the concept that we have called as a SUPEL (Straight Utilization of sPEnt LWR fuel in LWR system) scenario. Several spent BWR fuel compositions in loaded BWR fuel has been evaluated to achieve the criticality of reactor.

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Molten Salt Reactors and Thorium Energy

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Plutonium and minor actinides utilization in Thorium molten salt reactor

Cited by 4 publications

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Preliminary study on direct recycling of spent PWR fuel in PWR system

Preliminary study on direct recycling of spent PWR fuel in PWR system

Preliminary study on direct recycling of spent BWR fuel in BWR system

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