Study for Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (PBWFR)

Takahashi, Minoru; Hata, Kouji; Uchida, Shouji

doi:10.1299/jsmemecjo.2003.3.0_239

Cited by 6 publications

(7 citation statements)

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“…This concept was first proposed by Buongiorno . Takashima et al optimized the core design, extending the core lifetime, and making the structure more compact and transportable . The schematic diagram of PBWFR is shown in Figure .…”

Section: System Descriptionmentioning

confidence: 99%

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Sub-channel analysis for Pb-Bi-cooled direct contact boiling water fast reactor

et al. 2018

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Summary Pb‐Bi‐cooled direct contact boiling water fast reactor (PBWFR) featured with a direct‐contact heat exchanger between lead‐bismuth eutectic coolant and water could significantly simplify the primary system and enhance the natural circulation capability, meeting the potential needs for small modular reactor design. It is of great importance to conduct thermal‐hydraulic analysis of the PBWFR core in detail. In this paper, a self‐developed SUB‐channel AnalysiS code SUBAS is adopted to study the thermal hydraulic characteristics of the PBWFR core. The fidelity and the reliability of the code have been preliminarily benchmarked. With SUBAS, the space grid is studied to figure out its impact on the temperature and flow distributions in each sub‐channel. Besides, the application of space grids would increase the pressure drops and decreases the cross flow between adjacent sub‐channels. To study the transient performance of the PBWFR core, the power transient and the inlet blockage accident are calculated by SUBAS. The results of the power transient show the cross‐flow effect would be weakened in the sub‐channel which has higher coolant temperature and larger mass flow rate. For the inlet blockage accident, the results indicate the influence of the small area blockage is relatively weak on the overall performance of the assembly but is significant on the local parameters. With consideration of time and space, the blockage influence only exists in a certain area. This research may provide contribution to the design of PBWFR.

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Section: System Descriptionmentioning

confidence: 99%

“…12 Takashima et al optimized the core design, extending the core lifetime, and making the structure more compact and transportable. 13 The schematic diagram of PBWFR is shown in Figure 1. Liquid Pb-Bi alloy flows upward, removing the heat generated by the nuclear fuel.…”

Section: System Descriptionmentioning

confidence: 99%

Sub-channel analysis for Pb-Bi-cooled direct contact boiling water fast reactor

et al. 2018

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“…2) A Pb-Bi forced convection test loop 3) has been used to carry out a series of steel corrosion and flow technology tests [4][5][6] for the feasibility study of a Pb-Bi-cooled small fast reactor. 7) Previous studies have shown that LMC or oxidation corrosion occurs in steels in Pb-Bi at high temperature depending on the oxygen concentration in the liquid Pb-Bi, 4,8,9) although Pb-Bi is not so corrosive at low temperature no matter what the oxygen concentration is Refs. [10][11][12].…”

Section: Introductionmentioning

confidence: 98%

Metallurgical Analysis of a Tube Ruptured in the Lead Bismuth Corrosion Test Facility

Kondo¹,

Takahashi²

2006

J. Nucl. Sci. Technol.

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“…One of the key issues for the development of leadbismuth (Pb-Bi) cooled fast breeder reactors (FBRs) 1,2) is the compatibility of core and structural materials with PbBi flow at high temperature. 3) According to Gorynin et al,4) the compatibility of steels with Pb-Bi is dominated by two types of corrosion, i.e.…”

Section: Introductionmentioning

confidence: 99%

Corrosion of Steels in Lead-Bismuth Flow

Kondo

Takahashi

Sawada

et al. 2006

Journal of Nuclear Science and Technology

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For the development of lead-bismuth (Pb-Bi) cooled fast breeder reactors, the corrosion characteristics of various steels in a flowing Pb-Bi were investigated by means of steel corrosion test performed in the flowing Pb-Bi for 1,000 h. It was found that liquid metal corrosion was inhibited by single or multiple oxide layers formed on the steel surfaces. The oxide layers can be classified to an inner layer and an outer one. The existence of the inner oxide layer might be more important for the corrosion resistance since the inner one was compact and stuck to the steel surface while the outer one was easily broken into small pieces with cracks and peeled from the substrate. The effect of Cr content in steels on corrosion resistance was investigated. Stable Cr rich oxide layers were easily formed on the high Cr steels. The weight losses were lower in the steels with higher Cr contents. The content of Cr in the steel was effective to form the thin and compact Cr-rich oxide layer and suppressed the corrosion. In the case of Si rich steel, the weight loss was lower than the trends of weight loss with Cr content.

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Study for Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (PBWFR)

Cited by 6 publications

References 0 publications

Sub-channel analysis for Pb-Bi-cooled direct contact boiling water fast reactor

Sub-channel analysis for Pb-Bi-cooled direct contact boiling water fast reactor

Metallurgical Analysis of a Tube Ruptured in the Lead Bismuth Corrosion Test Facility

Corrosion of Steels in Lead-Bismuth Flow

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