Status report on the Small Secure Transportable Autonomous Reactor (SSTAR) /Lead-cooled Fast Reactor (LFR) and supporting research and development.

Sienicki, James J.; Moisseytsev, A.; Yang, Won Sik; Wade, David; Nikiforova, Anna; Hanania, P.; Ryu, Hyobong; Kulesza, K.; Kim, S. J.; Halsey, W.G.; Smith, Craig F.; Brown, Nils; Greenspan, E.; Caro, M.; Li, N.; Hosemann, Peter; Zhang, J.; Yu, Hyeonseung

doi:10.2172/932940

Cited by 22 publications

(18 citation statements)

References 14 publications

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“…Nitride fuel has high thermal conductivity, low neutron‐moderating ability, and high neutron economy, which makes it attractive in applications in a SMR. Plus, it has good chemical stability, good compatibility with liquid Pb‐Bi, and strong anti‐irradiation performance, which is good for the integrity of the fuel element in the Pb‐Bi fast reactor . Therefore, ThN and PuN are adopted.…”

Section: Reference Core Schemementioning

confidence: 99%

“…It is estimated to be higher than 1350°C. Therefore, in this paper, 1350°C is assumed to be the fuel temperature limit The cladding has to maintain its integrity; thus, the peaking cladding temperature should be strictly limited.…”

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%

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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%

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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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“…In the United States, the SSTAR reactor 20 is a lead-cooled small reactor (10-100 MWe) concept being developed by a team of national laboratories (Argonne, Lawrence Livermore, and Los Alamos) and the University of California at Berkeley (Fig. 5).…”

Section: Lead-cooled Reactorsmentioning

confidence: 99%

Reactor Technology Options Study for Near-Term Deployment of GNEP Grid-Appropriate Reactors

Ingersoll¹,

Poore²

2007

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“…Although some concept designs of the nuclear power generation systems utilized the S‐CO 2 power cycle, there are few studies on the coupling system of the pool‐type liquid metal cooled fast reactor and the S‐CO 2 cycle. Moisseytsev and Sienicki compared different layouts for the S‐CO 2 cycle coupled to the sodium‐cooled fast reactor.…”

Section: Introductionmentioning

confidence: 99%

Design and thermodynamic analysis of supercriticalCO₂reheating recompression Brayton cycle coupled with lead‐based reactor

Kong

et al. 2019

Int J Energy Res

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Summary A reheating process is generally incorporated in a supercritical CO2 (S‐CO2) Brayton cycle to enhance its efficiency. The heat transfer process from the reactor coolant to the working fluid of the power cycle is a key issue encountered when designing reheating power systems for the lead‐based reactor. The traditional reheating system, called RH‐1, utilizes an intermediate coolant circuit. In this paper, a novel reheating system, called RH‐2, is proposed. It eliminates the intermediate coolant circuit and combines the processes of the primary heating and reheating in a single heat exchanger. A thermodynamic analysis of three different systems for the lead‐based reactor integrated with the S‐CO2 power cycle with or without reheating was conducted to evaluate the performance of the proposed system. The results confirmed that the performance of RH‐2 was the best of all the three systems. Under the same reactor conditions, the system efficiency of RH‐2 was greater than those of RH‐1 and the recompression (no reheating) system by 1.2% and 1.7%, respectively. RH‐2 could also maintain higher efficiency when the main operating parameters varied. The efficiency of RH‐2 was higher at different core outlet temperatures and split ratios. The maximum efficiency at optimal maximum pressure of RH‐2 was greater than those of the other two systems. RH‐2 was less sensitive to the variations in the isentropic efficiencies of the components than the other two systems, while the turbine isentropic efficiency demonstrated a significantly higher impact on the system efficiency than the two compressors (approximately 3.8 times).

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Status report on the Small Secure Transportable Autonomous Reactor (SSTAR) /Lead-cooled Fast Reactor (LFR) and supporting research and development.

Cited by 22 publications

References 14 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

Reactor Technology Options Study for Near-Term Deployment of GNEP Grid-Appropriate Reactors

Design and thermodynamic analysis of supercriticalCO₂reheating recompression Brayton cycle coupled with lead‐based reactor

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Status report on the Small Secure Transportable Autonomous Reactor (SSTAR) /Lead-cooled Fast Reactor (LFR) and supporting research and development.

Cited by 22 publications

References 14 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

Reactor Technology Options Study for Near-Term Deployment of GNEP Grid-Appropriate Reactors

Design and thermodynamic analysis of supercriticalCO2reheating recompression Brayton cycle coupled with lead‐based reactor

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Design and thermodynamic analysis of supercriticalCO₂reheating recompression Brayton cycle coupled with lead‐based reactor