Design Study of Lead- and Lead-Bismuth-Cooled Small Long-Life Nuclear Power Reactors Using Metallic and Nitride Fuel

Sekimoto, Hiroshi; Su’ud, Zaki

doi:10.13182/nt109-307

Cited by 61 publications

(24 citation statements)

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“…Polonium-210 is very toxic and difficult to contain [7]. Nonetheless, the former Soviet Union developed and used PbBi-cooled reactors, and the PbBi-cooled approach has been proposed by several laboratories as an advanced power production reactor [17][18][19][20]. Bismuth possesses a higher melt temperature than the PbBi eutectic and offers no significant advantages over PbBi-cooled reactors.…”

Section: Heavy-metal Coolantsmentioning

confidence: 99%

An Assessment of Reactor Types for Thermochemical Hydrogen Production

Marshall¹

2002

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Nuclear energy has been proposed as a heat source for producing hydrogen from water using a sulfur-iodine thermochemical cycle. This document presents an assessment of the suitability of various reactor types for this application. The basic requirement for the reactor is the delivery of 900 C heat to a process interface heat exchanger. Ideally, the reactor heat source should not in itself present any significant design, safety, operational, or economic issues. This study found that Pressurized and Boiling Water Reactors, Organic-Cooled Reactors, and Gas-Core Reactors were unsuitable for the intended application. Although Alkali Metal-Cooled and Liquid-Core Reactors are possible candidates, they present significant development risks for the required conditions. Heavy Metal-Cooled Reactors and Molten Salt-Cooled Reactors have the potential to meet requirements, however, the cost and time required for their development may be appreciable. Gas-Cooled Reactors (GCRs) have been successfully operated in the required 900 C coolant temperature range, and do not present any obvious design, safety, operational, or economic issues. Altogether, the GCRs approach appears to be very well suited as a heat source for the intended application, and no major development work is identified. This study recommends using the Gas-Cooled Reactor as the baseline reactor concept for a sulfur-iodine cycle for hydrogen generation.4

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Section: Heavy-metal Coolantsmentioning

confidence: 99%

An Assessment of Reactor Types for Thermochemical Hydrogen Production

Marshall¹

2002

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“…There have been many studies Hong et al, 2005;Greenspan and ENHS Project Team, 2002;Sekimoto and Su'uD, 1995;Toshinsky, 1997;Toshinsky and Petrochenko, 2012;Smith et al, 2008) on the design of small long-life lead or lead-bismuth-cooled fast reactor cores. Many of them were targeted for long-life without refueling, the small size for transportability after fabrication in a factory, inherent safety, and proliferation resistance.…”

Section: Introductionmentioning

confidence: 99%

“…The coolant void worth is a relatively large positive under coolant voiding only for the active core and upper gas plenum. The other reactor core concept is the 150 MWt long-life core developed by the Tokyo Institute of Technology (TIT) group (Sekimoto and Su'uD, 1995). They designed long-life lead-bismuth-cooled cores by employing a small blanket region in the central region of the cores to achieve a very small burnup reactivity swing (<1$) over $12 EFPYs and to achieve negative coolant void reactivity.…”

Section: Introductionmentioning

confidence: 99%

A neutronic design study of lead-bismuth-cooled small and safe ultra-long-life cores

Kim

You

2015

Annals of Nuclear Energy

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“…Moreover, intensive and comprehensive research over the past decade already demonstrates that a CANDLE reactor maintains a lot of attractive merits [1][2][3][4][5][6], summarized in the following.…”

Section: Introductionmentioning

confidence: 99%

“…

Abstract: CANDLE (Constant Axial shape of Neutron flux, nuclide number densities and power shape During Life of Energy producing reactor) reactors have been intensively researched in the last decades [1][2][3][4][5][6]. Research shows that this kind of reactor is highly economical, safe and efficiently saves resources, thus extending large scale fission nuclear energy utilization for thousands of years, benefitting the whole of society.

…”

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confidence: 99%

Optimized Design and Discussion on Middle and Large CANDLE Reactors

Yan¹,

Zhang²,

Chai³

2012

Sustainability

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CANDLE (Constant Axial shape of Neutron flux, nuclide number densities and power shape During Life of Energy producing reactor) reactors have been intensively researched in the last decades [1][2][3][4][5][6]. Research shows that this kind of reactor is highly economical, safe and efficiently saves resources, thus extending large scale fission nuclear energy utilization for thousands of years, benefitting the whole of society. For many developing countries with a large population and high energy demands, such as China and India, middle (1000 MWth) and large (2000 MWth) CANDLE fast reactors are obviously more suitable than small reactors [2]. In this paper, the middle and large CANDLE reactors are investigated with U-Pu and combined ThU-UPu fuel cycles, aiming to utilize the abundant thorium resources and optimize the radial power distribution. To achieve these design purposes, the present designs were utilized, simply dividing the core into two fuel regions in the radial direction. The less active fuel, such as thorium or natural uranium, was loaded in the inner core region and the fuel with low-level enrichment, e.g. 2.0% enriched uranium, was loaded in the outer core region. By this simple core configuration and fuel setting, rather than using a complicated method, we can obtain the desired middle and large CANDLE fast cores with reasonable core geometry and thermal hydraulic parameters that perform safely and economically; as is to be expected from CANDLE. To assist in understanding the CANDLE reactor's attributes, analysis and discussion of the calculation results achieved are provided.

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Design Study of Lead- and Lead-Bismuth-Cooled Small Long-Life Nuclear Power Reactors Using Metallic and Nitride Fuel

Cited by 61 publications

References 1 publication

An Assessment of Reactor Types for Thermochemical Hydrogen Production

An Assessment of Reactor Types for Thermochemical Hydrogen Production

A neutronic design study of lead-bismuth-cooled small and safe ultra-long-life cores

Optimized Design and Discussion on Middle and Large CANDLE Reactors

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