Identification of safety gaps for fusion demonstration reactors

Wu, Yican; Chen, Z.; Hu, Lisha; Jin, Ming; Li, Y.; Jiang, Jieqiong; Yu, Jie; Alejaldre, C.; Stevens, Eef; Kim, K.; Maisonnier, D.; Kalashnikov, A.G.; Tobita, K.; Jackson, David; Perrault, Didier

doi:10.1038/nenergy.2016.154

Cited by 144 publications

(38 citation statements)

References 54 publications

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“…For the three samples, two diffraction peaks can be observed at 26. 6 and 55.0 . The peak located at 26.6 corresponds to the (002) plane and the peak at 55.0 can be assigned to the (004) plane.…”

Section: Effect Of Cations On the Exfoliation Efficiencymentioning

confidence: 98%

“…The above predictions indicate that nanoporous graphene is an excellent separation membrane for H/D/T isotopes and would nd applications in tritium production, tritium-containing waste processes in future fusion power plants, [6][7][8][9][10][11] and in dealing with nuclear accidents. Although the potential of isotope separation has been predicted, the mass manufacture of large-size graphene with appropriate pore size remains a great challenge.…”

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confidence: 99%

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Towards understanding the salt-intercalation exfoliation of graphite into graphene

Wang

Xiang

2017

RSC Adv.

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The preparation of graphene from graphite is critical for both theoretical studies and real-world applications. Herein, we present a systematic study to explore the fundamental factors that control the exfoliation of graphite into graphene in a salt-intercalation exfoliation system, using various inorganic salts as intercalators. The yields of the thin graphene sheets obtained, measured via UV-vis absorption spectrophotometry, suggest that both cations and anions significantly influence the exfoliation yields. Xray photoelectron spectroscopy and energy dispersive spectroscopy analysis showed that both anions and cations become inserted into the space between conjugated graphite layers during the intercalation process. X-ray diffraction spectra revealed that the anion can enhance the salt-intercalation exfoliation by expanding the interlayer spacing. Compared to lithium chloride, both potassium chloride and lithium sulfate can significantly enhance the exfoliation yields of graphene. Optimizing the cation and anion species can improve the yield of graphene, because co-intercalation with both anions and cations occurs during the intercalation process in the solution of inorganic salts. Our work provides a guide for rationally designing the salt-intercalation exfoliation procedure to obtain higher yields of exfoliated 2D materials.

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Section: Effect Of Cations On the Exfoliation Efficiencymentioning

confidence: 98%

mentioning

confidence: 99%

Towards understanding the salt-intercalation exfoliation of graphite into graphene

Wang

Xiang

2017

RSC Adv.

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“…To extract and transform fusion energy into electricity, a key component named blanket is needed . Liquid metal breeder blanket concepts are widely studied due to their high heat removal, adequate tritium breeding ratio, relative simple design, potential attractiveness of economy, and safety . Typical liquid PbLi beeder blanket concept has been explored extensively as a design option of DEMO blankets for fusion power reactors and test blanket modulus for ITER, such as the EU HCLL, US DCLL, and China DFLL .…”

Section: Introductionmentioning

confidence: 99%

A K-Epsilon RANS turbulence model for incompressible MHD flow at high Hartmann number in fusion liquid metal blankets

et al. 2017

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“…This has been proposed by different groups . Institute of Nuclear Energy Safety Technology (INEST/FDS Team), Chinese Academy of Science, made great progress in the development of lead‐cooled reactors in a wide spectrum of advanced nuclear energy technologies not only for fusion but also for advanced fission energy, such as fast reactor systems, small module reactor, and ADS …”

Section: Introductionmentioning

confidence: 99%

Large-scale energy production with thorium in a typical heavy-water reactor using high-grade plutonium as driver fuel

Şahi̇n

Şarer²

2018

Int J Energy Res

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Summary Thorium can be introduced into the energy vector in combination with high‐grade plutonium (HG‐Pu). Excellent neutron economy of heavy‐water moderator allows use of mixed ThO2/HG‐PuO2 fuel in heavy‐water reactors with high efficiency, leading to the exploitation of large world thorium reserves and extending the availability of the nuclear energy by two orders of magnitude. In the present work, the criticality calculations have been performed with the code MCNPX 3‐D geometrical modeling of a typical heavy‐water reactor, where the structure of all fuel rods and bundles is represented individually. In the course of time calculations, nuclear transformation and radioactive decay of all actinide elements as well as fission products are considered. Five different fuel compositions have been selected for investigations: (1) 97% thoria (ThO2) + 3% PuO2; (2) 96% ThO2 + 4% PuO2; (3) 95% ThO2 + 5% PuO2; (4) 94% ThO2 + 6% PuO2; and (5) 92% ThO2 + 8% PuO2. The behavior of the criticality k∞ and the burn‐up values of the reactor have been pursued by full power operation at 640 MWel (2180 MWth) for approximately 7 years. Time calculations have been conducted with MCNPX and CINDER codes under consideration of all nuclear transformation and radioactive decay processes on the actinide isotopes and fission fragments. As the reactor allows fuel recharging at on‐power operation mode, the reactor criticality has been followed down to keff,end = ~1.05. The corresponding burn‐up values and operation periods for the investigated modes are (1) 18 GWd/MT and 780 days; (2) 27 GWd/MT and 1200 days; (3) 35 GWd/MT and 1560 days; (4) 44 GWd/MT and 1940 days; and (5) 60 GWd/MT and 2640 days. Among the investigated four modes, 94% ThO2 + 6% PuO2 seems a reasonable choice under consideration of the high price of the HG‐Pu as driver fuel. The mixed fuel has the potential of an extensive exploitation of thorium resources. Reactor will run with the same fuel charge for approximately 5 years and allow a fuel burn‐up approximately 44 GWd/MT, comparable with conventional light‐water reactors (LWRs). Plutonium component of the mixed fuel will become nonprolific after few months of plant operation through the accumulation of even isotopes. Addition of few percent natural uranium to the initial mixed fuel charge will keep the 233U component below 22% and hence at nonprolific level over the entire plant operation period. Replacement of 4% ThO2 with 4% nat‐UO2 will practically not change main technical parameters of the reactor.

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Identification of safety gaps for fusion demonstration reactors

Cited by 144 publications

References 54 publications

Towards understanding the salt-intercalation exfoliation of graphite into graphene

Towards understanding the salt-intercalation exfoliation of graphite into graphene

A K-Epsilon RANS turbulence model for incompressible MHD flow at high Hartmann number in fusion liquid metal blankets

Large-scale energy production with thorium in a typical heavy-water reactor using high-grade plutonium as driver fuel

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