Influence of boron carbide on core degradation during severe accidents in LWRs

Steinbrück, M.

doi:10.1016/j.anucene.2013.09.027

Cited by 37 publications

(5 citation statements)

References 17 publications

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“…Control rods used in boiled-water reactors (BWRs) in Japan, including all units at the Fukushima Daiichi nuclear power plant (NPP), consist of stainless steel tubes filled with B 4 C granules 1 . B 4 C is stable at the normal NPP operating temperature of ~300 °C, as it melts at 2450 °C 2 . However, the eutectic interaction of B 4 C with the adjacent stainless steel leads to its liquefaction at temperatures exceeding 1200 °C under severe accidental conditions 1 2 3 4 5 .…”

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confidence: 99%

“…B 4 C is stable at the normal NPP operating temperature of ~300 °C, as it melts at 2450 °C 2 . However, the eutectic interaction of B 4 C with the adjacent stainless steel leads to its liquefaction at temperatures exceeding 1200 °C under severe accidental conditions 1 2 3 4 5 . The appearance of this liquid phase causes the phenomenon of candling and relocation, in which the liquid phase sinks to the bottom of the nuclear core.…”

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confidence: 99%

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Chemical State Mapping of Degraded B4C Control Rod Investigated with Soft X-ray Emission Spectrometer in Electron Probe Micro-analysis

Kasada

Higuchi³

et al. 2016

Sci Rep

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B4C is widely used as control rods in light water reactors, such as the Fukushima Daiichi nuclear power plant, because it shows excellent neutron absorption and has a high melting point. However, B4C can melt at lower temperatures owing to eutectic interactions with stainless steel and can even evaporate by reacting with high-temperature steam under severe accident conditions. To reduce the risk of recriticality, a precise understanding of the location and chemical state of B in the melt core is necessary. Here we show that a novel soft X-ray emission spectrometer in electron probe microanalysis can help to obtain a chemical state map of B in a modeled control rod after a high-temperature steam oxidation test.

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Chemical State Mapping of Degraded B4C Control Rod Investigated with Soft X-ray Emission Spectrometer in Electron Probe Micro-analysis

Kasada

Higuchi³

et al. 2016

Sci Rep

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“…It has been pointed out that the B4C in the control rods plays an important role in understanding the behavior of various elements around the core during the melting process. In particular, the eutectic reaction of B4C with the stainless steel (SS) control blade, as well as their interaction with zirconium cladding and channel box, is a key phenomenon that would be an indispensable factor in estimating the current reactor situation [1][2][3]. Recently, it has been indicated that the non-negligible amount of boron (B) in the control rods reacts with zirconium and iron in the core material, forming metallic borides [4].…”

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confidence: 99%

Development of an areal density imaging for boron and other elements

Tsuchikawa,

Kai,

Abe

et al. 2023

J. Phys.: Conf. Ser.

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Boron areal densities in pure boron samples were determined using energy-resolved neutron measurements. For non-destructive measurement of boron content, the neutron-energy spectrum was measured with prompt γ-ray activation analysis. It was confirmed that the areal density of samples could be measured with 1% to 10% accuracy for high boron content by neutron energy spectrum analysis. The viability of this analysis is also discussed compared with the traditional quantitative analysis.

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“…The meltdown sequence starts from the failure of control blades, which is initiated by the eutectic reaction between B 4 C and SS at approximately 1250 • C [2][3][4][5][6][7]. This temperature is far below the melting points of these components.…”

Section: Introductionmentioning

confidence: 99%

Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

Pham

Kurata

Steinbrueck

2021

Thermo

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Since the nuclear accident at Fukushima Daiichi Nuclear Power Station in 2011, a considerable number of studies have been conducted to develop accident tolerant fuel (ATF) claddings for safety enhancement of light water reactors. Among many potential ATF claddings, silicon carbide is one of the most promising candidates with many superior features suitable for nuclear applications. In spite of many potential benefits of SiC cladding, there are some concerns over the oxidation/corrosion resistance of the cladding, especially at extreme temperatures (up to 2000 °C) in severe accidents. However, the study of SiC steam oxidation in conventional test facilities in water vapor atmospheres at temperatures above 1600 °C is very challenging. In recent years, several efforts have been made to modify existing or to develop new advanced test facilities to perform material oxidation tests in steam environments typical of severe accident conditions. In this article, the authors outline the features of SiC oxidation/corrosion at high temperatures, as well as the developments of advanced test facilities in their laboratories, and, finally, give some of the current advances in understanding based on recent data obtained from those advanced test facilities.

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Influence of boron carbide on core degradation during severe accidents in LWRs

Cited by 37 publications

References 17 publications

Chemical State Mapping of Degraded B4C Control Rod Investigated with Soft X-ray Emission Spectrometer in Electron Probe Micro-analysis

Chemical State Mapping of Degraded B4C Control Rod Investigated with Soft X-ray Emission Spectrometer in Electron Probe Micro-analysis

Development of an areal density imaging for boron and other elements

Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

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