Irradiation tests and post-irradiation examinations of DUPIC fuel

Park, Chang Je; Kang, Kweon Ho; Ryu, Ho Jin; Lee, Cheol Yong; Jung, In‐Ha; Moon, Je Sun; Park, Joo Hwan; Na, Sang Ho; Song, Kiwon

doi:10.1016/j.anucene.2008.05.003

Cited by 6 publications

(3 citation statements)

References 10 publications

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“…The UO 2 with fission products and actinides is fabricated into PWR spent fuel assemblies. This separation process was adopted from DUPIC fuel process [4,8]. Finally, this spent PWR fuel assemblies are loaded into PWR core together with fresh enriched UO 2 fuel assemblies.…”

Section: Methodsmentioning

confidence: 99%

SUPEL Scenario for PWR Spent Fuel Direct Recycling Scheme

Waris

Pramuditya

Aji

et al. 2014

AMM

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Study on SUPEL (Straight Utilization of sPEnt LWR fuel in LWR system) scenario for PWR spent fuel direct recycling scheme has been performed. Several spent PWR fuel compositions in loaded fuel has been investigated to achive the criticality of reactor. The reactor can obtain it criticality for 4.5 a% of UO2 enrichment with at maximum 8.0 a% of spent fuel fraction in loaded fuel. The neutron spectra become harder with the raising of UO2 enrichment in the loaded fresh fuel as well as the increasing of the fraction of spent fuel in the core.

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Section: Methodsmentioning

confidence: 99%

SUPEL Scenario for PWR Spent Fuel Direct Recycling Scheme

Waris

Pramuditya

Aji

et al. 2014

AMM

View full text Add to dashboard Cite

show abstract

“…The UO 2 with fission products and actinides is fabricated into PWR spent fuel assemblies. This separation process was adopted from DUPIC fuel process [5,8]. Finally, this spent PWR fuel assemblies are loaded into PWR core together with fresh enriched UO 2 fuel assemblies.…”

Section: Methodsmentioning

confidence: 99%

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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“…The CANDU series of reactors developed by Atomic Energy of Canada Limited (AECL) is designed to use natural uranium, but it can also use low enriched uranium [129] or a variety of fuels, including fuel discharged from light water reactors [130], and thorium, in combination with uranium or plutonium [131][132][133]. CANDU reactors are refueled on-power, thus avoiding the need for a refueling outage typical of other designs.…”

Section: Gen Iii/iii+ Pressurized Heavy Water Reactorsmentioning

confidence: 99%

Review of Generation‐III/III+ Fission Reactors

Marques

2011

Nuclear Energy Encyclopedia

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Irradiation tests and post-irradiation examinations of DUPIC fuel

Cited by 6 publications

References 10 publications

SUPEL Scenario for PWR Spent Fuel Direct Recycling Scheme

SUPEL Scenario for PWR Spent Fuel Direct Recycling Scheme

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

Review of Generation‐III/III+ Fission Reactors

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