Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation

Shin, Yong-Hoon; Choi, Sungyeol; Cho, Jaehyun; Kim, Ji Hyun; Hwang, Il Soon

doi:10.1016/j.pnucene.2015.01.002

Cited by 32 publications

(22 citation statements)

References 31 publications

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“…Figure shows the temperature of the circulation system for the URANUS reactor components . Inlet plenum where LBE coolant enters has temperature about 300°C, while upper parts where heat exchange happens have temperature about 450°C.…”

Section: Resultsmentioning

confidence: 99%

“…Figure 13 shows the temperature of the circulation system for the URANUS reactor components. 5 Inlet plenum where LBE coolant enters has temperature about 300°C, while upper parts where heat exchange happens have temperature about 450°C. The range of temperature range from 300°C to 450°C is acceptable for safe operation of MHD coolant circulation system for the URANUS reactor considering structural material such as silicon steel, SUS 316, and copper.…”

Section: Resultsmentioning

confidence: 99%

“…Natural circulation is used in the primary cooling system using lead‐bismuth eutectic (LBE) coolant, which is composed of 44.5% lead and 55.5% bismuth at the full 100 MW t power of the reactor. The conceptual design of the GEN‐IV SMLFR called the ubiquitous, rugged, accident‐forgiving, nonproliferating, and ultralasting sustainer (URANUS) reactor has been under development at Seoul National University in Korea since 2011 and is depicted in Figure . The URANUS reactor is expected to use LBE as its coolant, where the coolant circulation must be forced, because natural circulation would not be certain to provide sufficient cooling.…”

Section: Introductionmentioning

confidence: 99%

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Development of innovative reactor-integrated coolant system design concept for a small modular lead fast reactor

Kwak

Kim

2018

Int J Energy Res

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Summary The report describes the development of an innovative magnetohydrodynamic (MHD) space‐integrated coolant system design concept for the small modular lead fast reactor called the ubiquitous, rugged, accident‐forgiving, nonproliferating, and ultralasting sustainer reactor. The coolant system efficiency was analyzed based on space‐integrated geometric and electromagnetic variables related to the circulation of lead‐bismuth eutectic (LBE) liquid metal coolant in a reactor with a thermal output of 100 MWt and using the MHD principle. The objective of the system is to optimize the circulation of the noncontacting liquid metal coolant without any internal structure, such as an impellor or sealing part, to transport the LBE with high electrical conductivity in the reactor. The concept was first applied to the pool‐type integral leading facility for lead‐alloy cooled advanced small modular reactor, which serves as a scaled‐down experimental facility for the ubiquitous, rugged, accident‐forgiving, nonproliferating, and ultralasting sustainer reactor, for characteristic analysis of the coolant system subject to the requirements of a developed pressure of 8456 Pa and a mass flow rate of 21.37 kg/second. The MHD core blanket, which was attached to the upper part of the pool‐type integral leading facility for lead‐alloy cooled advanced small modular reactor and wrapped it cylindrically from the outside to form an annular passage, was designed for the forced circulation of liquid LBE taking into account its internal space and the high operating temperature of 440°C. Design variable analysis provided the optimized geometric and electromagnetic parameters of the MHD driving system based on the electromagnetic characteristics in the coolant passage of the reactor. This forced cooling system concept based on MHD propulsion is structurally simple and will enable significant space reduction and increased power for small modular lead fast reactors. It was also determined that safe long‐term reactor operation could be ensured without requiring particular maintenance because the operation does not involve fluid contact.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Development of innovative reactor-integrated coolant system design concept for a small modular lead fast reactor

Kwak

Kim

2018

Int J Energy Res

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“…Low heat generation density is also an advantage for its safety and operation, because it mitigates the impacts of transients. In-core assembly arrangement of URANUS-40 core [5].…”

Section: Design Feature Of Uranusmentioning

confidence: 99%

Small modular reactor (SMR) development plan in Korea

Shin

Park

Kim

et al. 2015

AIP Conference Proceedings

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“…Currently, the internationally typical LFR concepts are listed as follows: The 3 reference LFR designs comprise ELFR (~1500 MWt/600 MWe) by Europe, BREST‐OD‐300 (700 MWt/300 MWe) by Russia, and SSTAR (45 MWt/20 MWe) by the USA; ALFRED (300 MWt/125 MWe) by Europe; LFR‐AS‐200 (200 MWe) by the USA; other reactors of STAR series by the USA, such as STAR‐H2; URANUS (50 MWe) by South Korea; SNCLFR‐100 (100 MWt) by China; MYRRHA (~100 MWt) by Europe; and so on.…”

Section: Introductionmentioning

confidence: 99%

Preliminary design of a medium-power modular lead-cooled fast reactor with the application of optimization methods

et al. 2018

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Summary Based on research and development experience from Gen III, Gen III+, and Gen IV reactor concepts, a 1000‐MWt medium‐power modular lead‐cooled fast reactor M2LFR‐1000 was developed by University of Science and Technology of China (USTC), aiming at achieving a reactor design fulfilling the Gen IV nuclear system requirements and meanwhile emphasizing application of optimization methods in preliminary design phase. By using the optimization methods presented, primarily considering the safety design limits (the maximum coolant velocity, the maximum cladding temperature, and the maximum burn‐up limited by the cladding radiation damage permitted), the preliminary design of 1000‐MWth medium‐power modular lead‐cooled fast reactor M2LFR‐1000 was carried out, including the design of fuel rods, fuel assemblies, reactivity control system, primary system, secondary system, decay heat removal system, and so on. The analysis of neutron characteristics (including reactivity feedback coefficients) and thermal hydraulics characteristics (the maximum fuel temperature and the maximum cladding outer surface temperature) of the core under normal steady‐state condition was carried out to evaluate the core design. Also, the analysis of 2 typical protected transients (protected transient over power accident and protected loss of flow accident) was conducted. Other analysis work of the reactor is to be done, such as the transient analysis via computational fluid dynamic codes and the seismic response analysis of the reactor. But the preliminary analysis results obtained so far under normal steady state and transient conditions confirm the inherent safety characteristics of the reactor design.

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Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation

Cited by 32 publications

References 31 publications

Development of innovative reactor-integrated coolant system design concept for a small modular lead fast reactor

Development of innovative reactor-integrated coolant system design concept for a small modular lead fast reactor

Small modular reactor (SMR) development plan in Korea

Preliminary design of a medium-power modular lead-cooled fast reactor with the application of optimization methods

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