Oxidation behavior of boronated graphite in helium, containing water vapor

Fujii, Kimio; Nomura, Shigeo; Imai, Hisashi; Shindo, Masami

doi:10.1016/0022-3115(92)90315-c

Cited by 7 publications

(4 citation statements)

References 5 publications

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“…3 central picture). This product is B 2 O 3 , the liquid formed from the B 4 C-steam reaction according to reaction (1) and observed by other authors [4,5,10,11,13,14]. During the tests, a significant release of vapour was noted.…”

Section: Experimental Results and Determination Of Kinetic Constantsmentioning

confidence: 62%

See 1 more Smart Citation

Investigation on boron carbide oxidation for nuclear reactor safety: Experiments in highly oxidising conditions

Domínguez¹,

Cocuaud²,

Drouan³

et al. 2008

Journal of Nuclear Materials

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Section: Experimental Results and Determination Of Kinetic Constantsmentioning

confidence: 62%

“…Available data on steam oxidation of boron carbide are highly dependent on samples shape and tests conditions [4,5,[10][11][12][13][14][15]. Up to now, only Steinbrü ck [4,14] studied French PWR boron carbide pellets.…”

Section: Kinetic Model Of B 4 C Oxidation Under Steam In Pellet Confimentioning

confidence: 99%

Investigation on boron carbide oxidation for nuclear reactor safety: Experiments in highly oxidising conditions

Domínguez¹,

Cocuaud²,

Drouan³

et al. 2008

Journal of Nuclear Materials

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“…Direct measurement of the impurity content of boron carbide from TREAT was not available. However, possible impurities might include those shown in Table 3.21 [Fujii 2003], which are quite negligible. Table 3.21.…”

Section: Composition and Impurity Contentmentioning

confidence: 99%

Baseline Assessment of TREAT for Modeling and Analysis Needs

Bess

DeHart

2015

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TREAT is an air-cooled, graphite moderated, thermal, heterogeneous test facility designed to evaluate reactor fuels and structural materials under conditions simulating various types of nuclear excursions and transient undercooling situations that could occur in a nuclear reactor. After 21 years in a standby mode, TREAT is being reactivated to revive transient testing capabilities. Given the time elapsed and the concurrent loss of operating experience, current generation and advanced computational methods are being applied to begin TREAT modeling and simulation prior to renewed at-power operations. Such methods have limited value in predicting the behavior of TREAT without proper validation. Hence, the U.S. DOE has developed a number of programs to support development of benchmarks for both critical and transient operations. Extensive effort has been expended at INL to collect detailed descriptions, drawing and specification for all aspects of TREAT, and to resolve conflicting data found through this process. This report provides a collection of these data, with updated figures that are significantly more readable than historic drawings and illustrations, compositions, and dimensions based on the best available sources. This document is not nor should it be considered to be a benchmark report. Rather, it is intended to provide one stop shopping, to the extent possible, for other work that seeks to prepare detailed, accurate models of the core and its components. Given the nature of the variety of historic documents available and the loss of institutional memory, the only completely accurate database of TREAT data is TREAT itself. Unfortunately, disassembly of TREAT for inspection, assay, and measurement is highly unlikely. Hence the data provided herein is intended serve as a best-estimate substitute.

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“…Several authors have shown that (i) low boron additions in graphite inhibit the oxidation of carbon and (ii) the formation of a molten B 2 O 3 glass acts as a physical barrier against oxygen diffusion for higher boron contents [10][11][12][13][14]. In a previous study of the physico-chemical properties of various C(B) materials [3], it has been reported that only a small amount of boron is needed (less than 8 at.…”

Section: Oxidation Resistancementioning

confidence: 99%

Untitled

Jacques

Guette

Langlais

et al. 1997

Journal of Materials Science

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A specific test procedure has been developed to compare the high temperature lifetimes in air and under load of SiC/SiC microcomposites with various interphases.The interphases, viz. pure pyrocarbon (PyC) or C(B) materials with different uniform or variable boron contents in the thickness, were prepared by CVD. Uniform addition of boron in PyC interphases improved their oxidation resistance and consequently the lifetimes of the microcomposites. However, room temperature tensile tests have shown that this improvement occurs to the detriment of the mechanical properties even when a non-brittle behaviour is maintained. In the case of variable boron contents, compositional gradient interphases (CGI) in which boron content increases from the fiber interface to the matrix interface allow to combine the mechanical fuse properties of PyC with the oxidation resistance of a C(B) material.

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Oxidation behavior of boronated graphite in helium, containing water vapor

Cited by 7 publications

References 5 publications

Investigation on boron carbide oxidation for nuclear reactor safety: Experiments in highly oxidising conditions

Investigation on boron carbide oxidation for nuclear reactor safety: Experiments in highly oxidising conditions

Baseline Assessment of TREAT for Modeling and Analysis Needs

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