Physics Study on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU (DUPIC)

Choi, Hangbok; Rhee, Bo Wook; Park, Hyunsoo

doi:10.13182/nse97-a24459

Cited by 50 publications

(16 citation statements)

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“…Additional extension of the fuel burnup might be achieved by changing the fuel cladding from stainless steel, whose absorption is rather significant, to zirconium alloy and removing some of the volatile and semi-volatile fission products. Recent achievements in DUPIC fuel cycle 10) indicate that this operation might be performed with only mechanical and thermal treatment. This technology does not envisage the separation of fission nuclides and therefore can be proposed for developing countries without proliferation concern of the nuclear materials.…”

Section: Discussionmentioning

confidence: 99%

“…The idea of synergism of different nuclear technologies, first promoted more than two decades ago 9) nowadays is entering into the engineering stage with the development of a PWR-to-CANDU fuel cycle best known as DUPIC. 10) Behind this is the fact that the concentration of fissile isotopes in conventional PWR spent fuel exceeds the 235 U content in fresh CANDU fuel. A similar double-strata approach forms the framework of the present study.…”

Section: Introductionmentioning

confidence: 99%

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Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors

Barchevtsev

Artisyuk

Ninokata

2002

Journal of Nuclear Science and Technology

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This paper is aimed at the development of a fuel cycle concept for host countries with a lack of nuclear infrastructure. To minimize plutonium proliferation concern the adoption of long-life core with no fuel radiochemical treatment on site is suggested. Current investigation relies upon light water reactor technology and plutonium-free fresh fuel. Erbium doped to uranium oxide (enrichment 19.8%) fuel is selected as the reference. Such a high enrichment is selected in attempt to approach the longest irradiation time in one batch mode. In addition to that, uranium enriched up to 20% does not consider as a nuclear material for direct use in weapon manufacture. A sequence of two irradiation cycles for the same fuel rods in two different light water reactors is the key feature of the advocated approach. It is found that the synergism of PWR and pressure tube graphite reactor offers fuel burnup up to 140 GWd/tHM without compromising safety characteristics. Being as large as 8% in the final isotopic vector, fraction of 238 Pu serves as an inherent protective measure against plutonium proliferation.

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors

Barchevtsev

Artisyuk

Ninokata

2002

Journal of Nuclear Science and Technology

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“…Recently, DUPIC (Direct use of spent PWR (pressurized water reactor) fuel in CANDU (CANadian Deuterium Uranium)) concept which adopts the simple dry pyrochemical processing has been developed in Korea. [8][9][10] The flow of the simple dry pyrochemical processing assumed in this study is shown in Fig. 2.…”

Section: Compound Process Fuel Cycle Conceptmentioning

confidence: 99%

Compound Process Fuel Cycle Concept and Core Characteristics

Ikegami¹

2006

J. Nucl. Sci. Technol.

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A new fuel cycle concept is proposed in which spent fuels of light water reactor are multi-recycled in a fast reactor core without ordinary reprocessing process but with only simple dry pyrochemical processing. Feasibility of the concept has been studied focusing on the core nuclear characteristics adopting radial heterogeneous core configuration in which both recycled light water spent fuels and fast reactor fuels are loaded. Results of the core survey analyses show that four to six time recycling of light water reactor spent fuels with the burn-up of 300 to 400 GWd/t can be achieved with almost no increase of minor actinide content. Such benefits will be expected in this concept, though further research and development efforts are required, as efficient utilization of nuclear fuel resources, enhancement of nuclear non-proliferation due to the fact that all actinides are recycled all together in a lumped state together with the fact that the concept has no radial blanket fuels which contain high fissile plutonium ratio, besides the possibilities of reduction of environmental impacts due to reduced high level waste, reduction of fuel cycle cost through simplified reprocessing procedure, and suppression of light water reactor spent fuel pile-up.

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“…The reason is that 35,000 MWd/MTU with initial enrichment of 3.5% 235 U was chosen as a reference PWR fuel in DUPIC fuel cycle development in Korea. 6,8) In PWR-MOX fuel cycle, the plutonium recovered from reprocessing of LEU PWR fuel is made into MOX fuel, which is burned in PWR, and then discharged MOX spent fuel is disposed of. In order to calculate how much plutonium is in PWR spent fuel burnt with 35,000 MWd/MTU, we have used ORIGEN 2 computer code.…”

Section: Reference Reactors and Fuelsmentioning

confidence: 99%

“…[5][6][7][8] The basic idea of this fuel cycle alternative is that the spent fuel from LWR contains enough fissile remnant to be burnt again in CANDUs (Canadian Deuterium Uranium, Reactors) by direct refabrication, without separating the residual fissile materials, before eventual disposal of the spent fuel. The DUPIC fuel cycle may offer a good alternative to other conventional options, considering the high proliferation resistance.…”

Section: Introductionmentioning

confidence: 99%

Analysis of Nuclear Proliferation Resistance of DUPIC Fuel Cycle

Kim

2001

Journal of Nuclear Science and Technology

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Physics Study on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU (DUPIC)

Cited by 50 publications

References 1 publication

Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors

Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors

Compound Process Fuel Cycle Concept and Core Characteristics

Analysis of Nuclear Proliferation Resistance of DUPIC Fuel Cycle

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