Pb Bi-cooled direct contact boiling water small reactor

Takahashi, Minoru; Uchida, Shoji; Hata, Koji; Matsuzawa, Tomohiro; Osada, Hiroo; Kasahara, Yoshiyuki; Sawa, Naoki; Okubo, Y.; Obara, Toru; Yusibani, Elin

doi:10.1016/j.pnucene.2005.05.020

Cited by 36 publications

(13 citation statements)

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“…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 direct‐contact‐Boiling Water Fast Reactor (PBWFR) has been developed . It is a 150 MWe modular reactor installed with a steam‐lift pump to enhance the natural circulation capability, thereby ensuring compact structure.…”

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: Introductionmentioning

confidence: 99%

“…In Japan, a conception of Pb-Bi cooled directcontact-Boiling Water Fast Reactor (PBWFR) has been developed. 13 It is a 150 MWe modular reactor installed with a steam-lift pump to enhance the natural circulation capability, thereby ensuring compact structure. However, the steam-lift pump would cause extra problems during the operation.…”

Section: Introductionmentioning

confidence: 99%

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

et al. 2019

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“…This issue, relevant to ferritic/martensitic steels in general, has not been addressed, in spite of many papers on the subject of oxidation behavior of ferritic/martensitic steels in lead-bismuth eutectic, including some recent ones [8,9]. Fortunately, ceramic coatings such as TiC, ZrC, SiC, Si3N4 and TiN have been reported to be effective in retarding the corrosion by LBE [10][11][12][13]. If the eliminated carbon can combine with titanium, a self-growing TiC coating will be formed on the surface of SIMP steel.…”

Section: Introductionmentioning

confidence: 99%

Corrosion resistance of self-growing TiC coating on SIMP steel in LBE at 600 °C

Shi

Yan

Sha

et al. 2016

Materials and Corrosion

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SIMP steel was newly developed as a candidate structural material for the accelerator driven subcritical system. The serious decarburization of SIMP steel because of the high Si content was used to successfully form a self-growing TiC coating on the surface, after the Ti deposition as a first step. This TiC layer can effectively protect the surface from the static liquid lead-bismuth eutectic (LBE) corrosion at 600 °C up to 2000 h in the low oxygen LBE.However, in the oxygen saturated LBE, the TiC coating is oxidized into porous TiO2 after only 500 h and fails to protect. Therefore, the self-growing TiC coating is desired only when the oxygen content of LBE is strictly controlled on a low level.

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“…Lead alloys are attractive candidate coolants and target materials for lead alloycooled fast reactors (LFR) and the accelerator driven system (ADS), respectively, where the lead alloy includes both of pure lead and lead-bismuth eutectic (LBE or 45%Pb-55%Bi). Feasibility studies of LFRs have been performed so far for the LBE-Cooled Long-Life Safe Simple Small Portable Proliferation-Resistant Reactor (LSPR) (53 MWe/150MWt) [1][2][3], the Pb-Bi-cooled Direct Contact Boiling Water Small Fast Reactor (PBWFR) (150MWe/450MWt) [4], etc. Various studies have been also performed for the development of LFRs.…”

Section: Introductionmentioning

confidence: 99%

Overview of recent studies related to lead-alloy-cooled fast reactors

Takahashi

Pramutadi

et al. 2012

AIP Conference Proceedings

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The recent progress of the studies related to LFRs are summarized. The compatibility of materials with lead alloys has been clarified under steady and transient temperature conditions. Higher Cr content, Si and Al addition and Al-Fe alloy-coating improved corrosion resistance. The Al-Fe alloy-coated steel was not corroded even high temperature transient conditions. The ceramics of SiC and and Si 3 N 4 are expected to be used as cladding material for high temperature LFR. For the consideration of mass transport, the diffusion coefficient of Ni could be measured using Capillary methods. A new bubble visualization method in LBE with gamma-ray radiography was developed. The thermal interaction of LBE and lead droplets with sub-cooled water, and the fragmentation of droplets were investigated, and the visualization of volatile liquid in high temperature liquid were achieved.

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Pb Bi-cooled direct contact boiling water small reactor

Cited by 36 publications

References 1 publication

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

Corrosion resistance of self-growing TiC coating on SIMP steel in LBE at 600 °C

Overview of recent studies related to lead-alloy-cooled fast reactors

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