Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator

Bortot, Sara; Moisseytsev, A.; Sienicki, James J.; Artioli, C.

doi:10.1016/j.nucengdes.2011.04.012

Cited by 53 publications

(20 citation statements)

References 5 publications

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“…Furthermore, the American Society of Mechanical Engineers (ASME) codified T91 steel (FMS) has been chosen as a candidate for structures exposed to high temperatures and corrosive coolant; T91 is also applied to the cladding material.…”

Section: Reference Core Schemementioning

confidence: 99%

“…An upper limit of 2 m/s is widely adopted in the design of a LFR To ensure effective natural circulation, the pressure drop of the core should be as low as possible. Negative reactivity feedback coefficients should be guaranteed to avoid fuel collapse under all transient conditions. To make the reactivity easy to control, the reactivity swing during the whole lifetime should be limited to less than 1$ …”

Section: Core Optimizationmentioning

confidence: 99%

“…However, pumps are still used in this design, which may enhance difficulties in the fabrication and maintenance of the equipment. In America, a series of Secure Transportable Autonomous Reactor (STAR) concepts were proposed by Argonne National Laboratory (ANL), including 45 MWt SSTAR and 300 MWt SUPERSTAR . SSTAR and SUPERSTAR both adopt 100% natural circulation.…”

Section: Introductionmentioning

confidence: 99%

“…In America, a series of Secure Transportable Autonomous Reactor (STAR) concepts were proposed by Argonne National Laboratory (ANL), including 45 MWt SSTAR and 300 MWt SUPERSTAR. 10,11 SSTAR and SUPERSTAR both adopt 100% natural circulation. SSTAR uses tighter triangular pitch, while SUPERSTAR uses square pitch to increase the natural circulation capability.…”

Section: Introductionmentioning

confidence: 99%

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Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor

et al. 2019

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Summary Lead‐based fast reactors (LFRs) have unique advantages in the development of a SMR, which has attracted a lot of attention in recent years. In this paper, an optimized design for a lead‐bismuth small modular reactor was studied on the basis of the design of SUPERSTAR. This paper aims to propose an improved LFR core scheme to enhance the neutronic performance as well as the thermal‐hydraulic safety of the reference reactor. Advanced nitride fuel is adopted in which the plutonium is used as the driven fuel, while thorium is used as the fertile fuel. Subchannel analysis was performed in the assembly design using an in‐house subchannel code, SUBAS, and an 11 × 11 scheme with a pitch‐to‐diameter (P/D) ratio of 1.4 was chosen. Using the modified assembly, the core was redesigned using the coupled code MCORE. The active core was divided into four zones with different enrichment of 239Pu to extend the core lifetime and flatten the power distribution. The main kinetic parameters and reactivity coefficients were obtained. Neutronic performance at different operation times was also studied. The maximum radial power peak factor was 1.28, while the maximum total power peak factor was 1.737. During the whole lifetime, the reactivity swing was 0.926$, which was below the limit of 1$. The subchannel study of the core flow distribution showed that a flow distributor is needed to further improve the flow distribution capability. The peaking cladding temperature was 508.7°C, and the maximum fuel center temperature was 723.4°C, both of which do not exceed the limit temperature. Compared with features of SUPERSTAR, the peaking cladding temperature was well improved and the lifetime extended.

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Section: Reference Core Schemementioning

confidence: 99%

Section: Core Optimizationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor

et al. 2019

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“…On account of the nice natural circulation performances of lead or LBE, some natural circulation lead-or LBEcooled fast reactors have been researched and developed. In United States, several natural circulation lead-cooled fast reactors were developed in Argonne National Laboratory (ANL), such as SSTAR (Smith et al, 2008), SUPERSTAR (Bortot et al, 2011). In China, based on the past research and development work in advanced nuclear energy system (Wu et al, 1999(Wu et al, , 2002Wu and FDS Team, 2006, 2007, 2009Qiu et al, 2000;Wu, 2007), FDS team developed a natural circulation LBE-cooled fast reactor.…”

Section: Introductionmentioning

confidence: 99%

Transient analyses on loss of heat sink and overpower transient of natural circulation LBE-cooled fast reactor

Wang

et al. 2015

Progress in Nuclear Energy

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Generation IV Nuclear Reactors

Schulenberg

2003

Digital Encyclopedia of Applied Physics

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Generation IV nuclear reactors are a class of innovative nuclear reactors using technologies beyond pressurized water reactors or boiling water reactors, the basis of the current commercial nuclear power. Six different concepts have been selected by an international forum to be studied, developed, and eventually built in international collaboration. Among these are advanced water‐cooled reactors, which are intended to be more economical high‐temperature reactors providing process heat in addition to electric power production, fast reactors to recycle spent fuel to fissile material and to reduce the radioactive inventory of the spent fuel repository, and molten salt reactors with highest flexibility for future fissile materials. While some of these reactor technologies have already been built and operated, in principle, since several decades, others are entirely new. Actual concepts, technologies, and future challenges are discussed in the chapter.

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Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator

Cited by 53 publications

References 5 publications

Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor

Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor

Transient analyses on loss of heat sink and overpower transient of natural circulation LBE-cooled fast reactor

Generation IV Nuclear Reactors

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