Towards an intrinsically safe and economic thorium breeder reactor

Jagannathan, V.; Pal, Usha

doi:10.1016/j.enconman.2006.02.008

Cited by 16 publications

(6 citation statements)

References 3 publications

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“…The reactor design to enable high rate of thorium conversion to fissile 233 U has been named as “A Thorium Breeder Reactor” (ATBR). A conceptual 600‐MWe reactor design was studied with enriched UO 2 as seed driver material . Other seed materials like RG Pu and in a futuristic design with 233 U as fissile seed have also been studied .…”

Section: What Is Thorium Breeder?mentioning

confidence: 99%

“…A conceptual 600-MWe reactor design was studied with enriched UO 2 as seed driver material. 8,9 Other seed materials like RG Pu and in a futuristic design with 233 U as fissile seed have also been studied. 10 The main feature of the ATBR equilibrium core design is a flat excess reactivity at nominal power for a fuel cycle period of 1 or 2 years with literally no external control maneuvers and intrinsically flat power distribution.…”

Section: Conceptual Atbr 600-mwe Core Designmentioning

confidence: 99%

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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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Section: What Is Thorium Breeder?mentioning

confidence: 99%

Section: Conceptual Atbr 600-mwe Core Designmentioning

confidence: 99%

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

Jagannathan

2017

Int J Energy Res

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“…In order to simplify the mechanical design, we need to think out another way to keep CVR negative. Introducing thorium fuel is a possible option [4,[9][10][11], so this paper work mainly focuses on it.…”

Section: Scfr Conceptual Designmentioning

confidence: 99%

A Simplified Supercritical Fast Reactor with Thorium Fuel

Zhang

Wang

2014

Science and Technology of Nuclear Installations

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Super-Critical water-cooled Fast Reactor (SCFR) is a feasible option for the Gen-IV SCWR designs, in which much less moderator and thus coolant are needed for transferring the fission heat from the core compared with the traditional LWRs. The fast spectrum of SCFR is useful for fuel breeding and thorium utilization, which is then beneficial for enhancing the sustainability of the nuclear fuel cycle. A SCFR core is constructed in this work, with the aim of simplifying the mechanical structure and keeping negative coolant void reactivity during the whole core life. A core burnup simulation scheme based on Monte Carlo lattice homogenization is adopted in this study, and the reactor physics analysis has been performed with DU-MOX and Th-MOX fuel. The main issues discussed include the fuel conversion ratio and the coolant void reactivity. The analysis shows that thorium-based fuel can provide inherent safety for SCFR without use of blanket, which is favorable for the mechanical design of SCFR.

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“…This reactor was based on an advanced CANDU reactor type. 17) This study was conducted using the thorium and plutonium fuel system with a core blanket system. Those previous works show the feasibility of breeding in the thermal energy region fueled by 233 U-Th with some heterogeneous core for achieving breeding conditions.…”

Section: Introductionmentioning

confidence: 99%

Breeding Capability and Void Reactivity Analysis of Heavy-Water-Cooled Thorium Reactor

Permana

Takaki

Sekimoto

2008

Journal of Nuclear Science and Technology

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The fuel breeding and void reactivity coefficient of thorium reactors have been investigated using heavy water as coolant for several parametric surveys on moderator-to-fuel ratio (MFR) and burnup. The equilibrium fuel cycle burnup calculation has been performed, which is coupled with the cell calculation for this evaluation. The of 233 U shows its superiority over other fissile nuclides in the surveyed MFR ranges and always stays higher than 2.1, which indicates that the reactor has a breeding condition for a wide range of MFR. A breeding condition with a burnup comparable to that of a standard PWR or higher can be achieved by adopting a larger pin gap (1-6 mm), and a pin gap of about 2 mm can be used to achieve a breeding ratio (BR) of 1.1. A feasible design region of the reactors, which fulfills the breeding condition and negative void reactivity coefficient, has been found. A heavy-water-cooled PWR-type Th-233 U fuel reactor can be designed as a breeder reactor with negative void coefficient.

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Towards an intrinsically safe and economic thorium breeder reactor

Cited by 16 publications

References 3 publications

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

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

A Simplified Supercritical Fast Reactor with Thorium Fuel

Breeding Capability and Void Reactivity Analysis of Heavy-Water-Cooled Thorium Reactor

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