PASCAR: Long burning small modular reactor based on natural circulation

Choi, Sungyeol; Cho, Jaehyun; Bae, Moo-Hoon; Lim, Jun; Puspitarini, Dina; Jeun, Ji Hoon; Joo, Han Gyu; Hwang, Il Soon

doi:10.1016/j.nucengdes.2011.03.005

Cited by 54 publications

(15 citation statements)

References 28 publications

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“…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%

“…To make the reactivity easy to control, the reactivity swing during the whole lifetime should be limited to less than 1$. 10,12,25…”

Section: Core Design Constraintsmentioning

confidence: 99%

“…In 2008, a 30 MWe long-life SMR PASCAR (Proliferationresistant, Accident-tolerant, Self-supported, Capsular, and Assured Reactor) has been proposed by Korean researchers for remote deployment either as a single unit or in a cluster for electricity generation, heat supply, sea water desalination, or hydrogen production. 12 It uses LBE coolant and U-TRU-Zr metallic fuels, and it intends to achieve 20-year cycle length with 100 MWt full power operation. In Japan, a conception of Pb-Bi cooled directcontact-Boiling Water Fast Reactor (PBWFR) has been developed.…”

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: Core Optimizationmentioning

confidence: 99%

“…To make the reactivity easy to control, the reactivity swing during the whole lifetime should be limited to less than 1$. 10,12,25…”

Section: Core Design Constraintsmentioning

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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“…Existing nuclear battery concepts, from which many of the ideas of this study are based or inspired, include the ENHS (Encapsulated Nuclear Hear Source) [1], ARC-100 (Advanced Reactor Concepts-100) [2], AFR-100 (Advanced Fast Reactor-100) [3], SMFR (Small Modular Fast Reactor) [4], PEACER (Proliferation-resistant, Environment-friendly, Accident-tolerant, Continual and Economical Reactor) [5], Toshiba 4S (Super-Safe, Small and Simple) [6] and S-STAR (Secure, Transportable, Autonomous Reactor) [7]. Section 2 summarizes the basis for the core design study, including general design choices and the layout of the core.…”

Section:  Enhanced Safety Features (Robustness)mentioning

confidence: 99%

Optimizing the Design of Small Fast Spectrum Battery-Type Nuclear Reactors

Qvist

2014

Energies

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This study is focused on defining and optimizing the design parameters of inherently safe "battery" type sodium-cooled metallic-fueled nuclear reactor cores that operate on a single stationary fuel loading at full power for 30 years. A total of 29 core designs were developed with varying power and flow conditions, including detailed thermal-hydraulic, structural-mechanical and neutronic analysis. Given set constraints for irradiation damage, primary cycle pressure drop and inherent safety considerations, the attainable power range and performance characteristics of the systems are defined. The optimum power level for a core with a coolant pressure drop limit of 100 kPa and an irradiation damage limit of 200 DPA (displacements per atom) is found to be 100 MWt/40 MWe. Raising the power level of an optimized core gives significantly higher attainable power densities and burnup, but severely decreases safety margins and increases the irradiation damage. A fully optimized inherently safe battery-type fast reactor core with an active height and diameter of 150 cm (2.6 m 3 ), a pressure drop limit of 100 kPa and an irradiation damage limit of 300 DPA can be designed to operate at 150 MWt/60 MWe for 30 years, reaching an average discharge burnup of 100 MWd/kg-actinide.

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“…Based on the PEACER design, a small transmutation power unit called PASCAR was developed by NUTRECK in 2010 [3]. By utilizing outstanding natural circulation and chemical inertness with air and water of LBE coolant, the PASCAR design can employ a pool-type encapsulated reactor which includes a core of U-TRU-Zr-alloy fuel rods in open-square lattice and in-vessel steam generators without pumps.…”

Section: Introductionmentioning

confidence: 99%