Reactor physics ideas to design novel reactors with faster fissile growth

Jagannathan, V.; Pal, Usha; Karthikeyan, R.; Raj, Devesh; Srivastava, Ankit; Khan, Suhail Ahmad

doi:10.1016/j.enconman.2008.02.019

Cited by 9 publications

(7 citation statements)

References 7 publications

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“…Duplex core with the mixed coolant, in fact, exhibits ∼2% longer core life compared to the all-UO 2 core (consistent with findings with the H 2 O coolant) because of the higher thermal fertile-to-fissile thermal absorption ratio (Fig. 15) of the duplex core (Jagannathan et al, 2008). In addition, it can be also observed in Fig.…”

Section: Whole-core Feasibility Of the Mixed Coolantsupporting

confidence: 80%

Neutronic feasibility of civil marine small modular reactor core using mixed D2O+H2O coolant

Alam

Almutairi

Kumar

et al. 2020

Nuclear Engineering and Design

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In an effort to decarbonize the marine sector, there are growing interests in replacing the contemporary, traditional propulsion systems with nuclear propulsion systems. The latter system allows freight ships to have longer intervals before refueling; subsequently, lower fuel costs, and minimal carbon emissions. Nonetheless, nuclear propulsion systems have remained largely confined to military vessels. It is highly desirable that a civil marine core not to use highly enriched uranium, but it is then a challenge to achieve long core lifetime while maintaining reactivity control and acceptable power distributions in the core. The objective of this study is to design a civil marine core type of single batch small modular reactor (SMR) with low enriched uranium (LEU) (<20% 235 U enrichment), a soluble-boron-free (SBF) and using mixed D 2 O+H 2 O coolant for operation period over a 20 years life at 333 MWth. Changing the coolant properties is the way to alter the neutron energy spectrum in order to achieve a self-sustaining core design of higher burnup. Two types of LEU fuels were used in this study: micro-heterogeneous ThO 2 -UO 2 duplex fuel (18% 235 U enriched) and all-UO 2 fuel (15% 235 U enriched). 2D Assembly designs are developed using WIMS and 3D whole-core model is developed using PANTHER code. The duplex option shows greater promise in the final burnable poison design with high thickness ZrB 2 integral fuel burnable absorber (IFBA) while maintaining low, stable reactivity with minimal burnup penalty. For the final poison design with ZrB 2 , the duplex contributes ∼2.5% more initial

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Section: Whole-core Feasibility Of the Mixed Coolantsupporting

confidence: 80%

Neutronic feasibility of civil marine small modular reactor core using mixed D2O+H2O coolant

Alam

Almutairi

Kumar

et al. 2020

Nuclear Engineering and Design

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“…10,11 High neutron economy of heavy-water-moderated Canada Deuterium Uranium (CANDU) reactors promises to be an attractive option for the exploitation of rich world thorium reserves, which was subject of different work. [12][13][14][15][16][17][18][19][20][21] In a series of systematic studies conducted with the SCALE5 code package, 22 the utilization potential of HG-Pu, reactor-grade plutonium (RG-Pu), and minor actinides (MA) as mixed with thorium in CANDU reactors has been investigated. [23][24][25][26] These generic studies had been performed with the help of the SCALE5 code 22 in 1-D cylindrical geometry and S 8 -P 3 approximation using 238 groups' neutron cross sections of the ENDF-V data library under consideration of the transmutation and radioactive decay of all actinide isotopes.…”

Section: Discussionmentioning

confidence: 99%

“…High neutron economy of heavy‐water–moderated Canada Deuterium Uranium (CANDU) reactors promises to be an attractive option for the exploitation of rich world thorium reserves, which was subject of different work . In a series of systematic studies conducted with the SCALE5 code package, the utilization potential of HG‐Pu, reactor‐grade plutonium (RG‐Pu), and minor actinides (MA) as mixed with thorium in CANDU reactors has been investigated .…”

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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“…The thorium breeder principles used in the ATBR design are generic in nature and in principle can be applied to any type of reactor system. One study was reported in fast neutron spectrum . That reactor was called fast thorium breeder reactor (FTBR).…”

Section: Fast Thorium Breeder Reactormentioning

confidence: 99%

“…One study was reported in fast neutron spectrum. 23 That reactor was called fast thorium breeder reactor (FTBR). The principle is to load fertile material without any externally fed fissile material in internal blankets or fissile breeding zones.…”

Section: Fast Thorium Breeder Reactormentioning

confidence: 99%

Thorium breeder reactors as a power source for 21st century and beyond

Jagannathan

2017

Int J Energy Res

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SummaryTo meet the world energy demands, all forms of renewable energy sources should be exploited to reduce and possibly eliminate the presently predominant use of chemical energy source of fossil fuels that have a high rate of carbon emission. Nuclear energy from fission reactors is well established. It has less carbon footprint and also has the advantage of continuous base load supply compared with other renewable like solar or wind energy. Public acceptance of nuclear energy is being regained with wide institutional support for ensuring highest level of safety in Gen-III+ reactors. The R&D on innovative types of nuclear design is also essential to enable both growth and sustenance of nuclear energy. It is necessary to explore ways and means of the complete utilization of both fissile and fertile components of the nuclear fuel, which is possible only through closing of the fuel cycle and allowing multiple reuse of the fuel.Induction of fertile thorium and the depleted uranium in large measure would widen the nuclear material base and ensure energy supply for centuries. The idea of thorium breeders discussed and presented by the author can be studied by several competent groups world over. After a comprehensive research, they can be deployed to provide energy for the 21st century and beyond.

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Reactor physics ideas to design novel reactors with faster fissile growth

Cited by 9 publications

References 7 publications

Neutronic feasibility of civil marine small modular reactor core using mixed D2O+H2O coolant

Neutronic feasibility of civil marine small modular reactor core using mixed D2O+H2O coolant

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

Thorium breeder reactors as a power source for 21st century and beyond

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