A study on transmutation of LLFPs using various types of HTGRs

Kora, Kazuki; Nakaya, Hiroyuki; Matsuura, Hideaki; Goto, Minoru; Nakagawa, Shigeaki; Shimakawa, Satoshi

doi:10.1016/j.nucengdes.2016.01.030

Cited by 9 publications

(4 citation statements)

References 8 publications

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“…Lastly, in order to investigate the potential of high temperature gas-cooled reactors (HTGRs) for transmutation of long-lived fission products (LLFPs), numerical simulation of four types of HTGRs was carried out. An efficient LLFP transmutation using the Clean Burn without MA (minor actinides) proved to achieve very high burn-ups and producing the transmutation [19].…”

Section: Japan Atomic Energy Agency (Jaea)mentioning

confidence: 99%

The Strategy to Support HTGR fuels for The 10 MW Indonesia's Experimental Power Reactor (RDE)

Taryo

Ridwan²,

Sunaryo³

et al. 2018

urania

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STRATEGY TO SUPPORT HTGR FUEL FOR THE 10 MW INDONESIA'S EXPERIMENTAL POWER REACTOR (RDE). The Indonesia's 10 MW experimental power reactor (RDE) is developed based on high temperature gas-cooled reactor (HTGR) and the program of the RDE was firstly introduced to the Agency for National Development Planning (BAPPENAS) at the beginning of 2014. The RDE program is expected to have positive impacts on community prosperity, self-reliance and sovereignty of Indonesia. The availability of RDE will be able to accelerate advanced nuclear power technology development and hence elevate Indonesia to be the nuclear champion in the ASEAN region. The RDE is expected to be operable in 2022/2023. In terms of fuel supply for the reactor, the first batch of RDE fuel will be inclusive in the RDE engineering, procurement and construction (RDE-EPC) contract for the assurance of the RDE reactor operation from 2023 to 2027. Consideration of RDE fuel plant construction is important as RDE can be the basis for the development of reactors of similar type with small-medium power (25 MWe-200/300 MWe), which are preferable for eastern part of Indonesia. To study the feasibility of the construction of RDE fuel plant, current state of the art of the R&D on HTGR fuel in some advanced countries such as European countries, the United States, South Africa and Japan will be discussed and overviewed to draw a conclusion about the prospective countries for supporting the fuel for long-term RDE operation. The strategy and roadmap for the preparation of the RDE fuel plant construction with the involvement of national stakeholders have been developed. The best possible vendor country to support HTGR fuel for long-term operation is finally accomplished. In the end, this paper can be assigned as a reference for the planning and construction of HTGR RDE fuel fabrication plant in Indonesia.Keywords: RDE, Indonesia, HTGR, fuel, strategy.

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Section: Japan Atomic Energy Agency (Jaea)mentioning

confidence: 99%

The Strategy to Support HTGR fuels for The 10 MW Indonesia's Experimental Power Reactor (RDE)

Taryo

Ridwan²,

Sunaryo³

et al. 2018

urania

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“…e results show that LLFP and MA perfectly transmute in the fast reactor. Kora et al [8] consider 4 different HTGR to convert LLFPs. eir aim is LLFP transmutation and storage, and they realize effective LLFP transmutation.…”

Section: Introductionmentioning

confidence: 99%

Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System

Arslan

Yilmaz

Bakır

et al. 2019

Science and Technology of Nuclear Installations

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This study presents the time-dependent analyses of transmutations of long-lived fission products (LLFPs) and medium-lived fission products (MLFPs) occurring in thermal reactors in a conceptual helium gas-cooled accelerator-driven system (ADS). In accordance with this purpose, the CANDU-37 and PWR 15 × 15 spent fuels are separately considered. The ADS consists of LBE-spallation neutron target, subcritical fuel zone, and graphite reflector zone. While the considered ADS is fueled with the spent nuclear fuels extracted from each thermal reactor without the use of additional fuel, fission products extracted from same thermal reactor are also placed into transmutation zone in graphite reflector zone. The LLFP transmutation performance of the modified ADS is analyzed by considering three different spent fuels extracted from the thermal reactors. Spent fuels are extracted from CANDU-37 in case A, from PWR-15 × 15 in case B, and from CANDU-37 fueled with mixture of PWR 15 × 15 spent fuel and 46% ThO2 in case C. The LBE target is bombard with protons of 1000 MeV. The proton beam power is assumed as 20 MW, which corresponds to 1.24828·1017 protons per second. MCNPX 2.7 and CINDER 90 computer codes are used for the time-dependent burn calculations. The ADS is operated under subcritical mode until the value of keff increases to 0.984, and the maximum operation times are obtained as 3400, 3270, and 5040 days according to the spent fuel cases of A, B, and C, respectively. The calculations bring out that in the modified ADS, LLFPs and MLFPs, which are extracted from thermal reactors, can be transformed to stable isotopes in significant amounts along with energy production.

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“…Nuclear power generation has produced as by-products, large inventories of fissile and burnable extremely long-lived isotopes of the transuranic elements (Np, Pu, Am and Cm) as well as long-lived fission products, including, but not limited to, 99 Tc, 93 Zr, 135 Cs, 107 Pd and 129 I) [1,2]. The above mentioned transuranics together are responsible for long-term decay heat generation and radiotoxicity.…”

Section: Introductionmentioning

confidence: 99%

“…Nevertheless many technical challenges need to be overcome before Minor Actinide transmutation can be implemented. Of the long-lived fission products, the transmutation of 99 Tc, ( 99 Tc + n → 100 Ru +  − ) is generally considered technically feasible, although it has received much less attention [1,6]. The current work attempts to address target materials for the transmutation of 99 Tc.…”

Section: Introductionmentioning

confidence: 99%

Porous Zr2SC-carbon composite microspheres: Possible radiation tolerant sorbents and transmutation hosts for technetium-99

Scales

Aughterson

Karatchevtseva

et al. 2018

Microporous and Mesoporous Materials

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The preparation, characteristics and adsorption properties of novel porous carbon-ceramic composite microspheres are presented. The composites were synthesised by a simple ion exchange process involving the cationic Zr tetramer and commonly-available macroporous sulphonated polystyrenedivinylbenzene cation exchange resins, with subsequent carbothermal reduction at 1350 °C. The materials were extensively characterised with respect to composition, chemical structure and porosity. Carbothermal reduction of the Zr-loaded templates resulted in formation of crystallites of the MAX phase zirconium sulphide carbide (Zr 2 SC) embedded within a highly microporous carbon framework with a macroporous secondary structure inherited from the resin template. Despite the high BET surface areas of the Zr 2 SC-carbon composite microspheres (in some cases, greater than 600 m 2 g −1), they are extremely mechanically robust. The microspheres displayed high adsorption selectivity for oxoanions relative to cationic solution species, including perrhenate (ReO 4 −), a pertechnetate (TcO 4 −) surrogate. Accumulation of ReO 4 − on the Zr 2 SC particles was unequivocally demonstrated by elemental mapping. Such materials are potential candidates as combined 99 Tc sorbents and reusable transmutation hosts.

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A study on transmutation of LLFPs using various types of HTGRs

Cited by 9 publications

References 8 publications

The Strategy to Support HTGR fuels for The 10 MW Indonesia's Experimental Power Reactor (RDE)

The Strategy to Support HTGR fuels for The 10 MW Indonesia's Experimental Power Reactor (RDE)

Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System

Porous Zr2SC-carbon composite microspheres: Possible radiation tolerant sorbents and transmutation hosts for technetium-99

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