B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments

Repetto, G.; Luze, O. de; Seiler, Nathalie; Trambauer, K.; Austregesilo, H.; Birchley, J.; Ederli, S.; Lamy, Jean-Sylvestre; Maliverney, B.; Drath, T.; Hollands, T.

doi:10.1016/j.pnucene.2009.09.017

Cited by 18 publications

(2 citation statements)

References 6 publications

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“…The possible chemical reactions are as follows [20] . The physical property data of the related chemical compounds and alloy are given in Table 3.…”

Section: Formation Of Csbo 2 and Releasementioning

confidence: 99%

Examination of ¹³¹I and ¹³⁷Cs releases during late phase of Fukushima Daiichi NPP accident by using ¹³¹I/¹³⁷Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Hidaka

Yokoyama

2017

Journal of Nuclear Science and Technology

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To investigate what happened in reality during the Fukushima Daiichi Nuclear Power Plant accident, the phenomena within reactor pressure vessel and the discussion of ties with the environmental monitoring measurement are very important. However, the previous study that treats phenomena of the both has not necessarily advanced up to the present time. The source terms predicted by simulation codes such as MELCOR has not yet been consistent with the reverse estimation by WSPEEDI code using environmental measurement data. The present study investigated 131 I and 137 Cs release behaviors during the late phase of the accident to contribute to such examination using the 131 I/ 137 Cs ratio of the new source terms predicted by Katata. The 131 I release by the gas-liquid partition from the contaminated water in the 1F2 and 1F3 reactor buildings which was pointed out in the previous study was reevaluated using the new source terms. In addition, paying attention to the similarity of the core conditions between the

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“…The possible chemical reactions are as follows [20] . The physical property data of the related chemical compounds and alloy are given in Table 3.…”

Section: Formation Of Csbo 2 and Releasementioning

confidence: 99%

Examination of ¹³¹I and ¹³⁷Cs releases during late phase of Fukushima Daiichi NPP accident by using ¹³¹I/¹³⁷Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Hidaka

Yokoyama

2017

Journal of Nuclear Science and Technology

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“…In a B 4 C oxidation process, similar to Zr oxidation, not only are large amounts of reaction heat and H 2 generated, but also CO, CO 2 , and CH 4 that may influence the chemical forms of iodine. The main chemical reactions are listed along with the Zr oxidation reaction formula, as follows: 5,6) Oxidation of B 4 C 5) (1) 342 INSIGHTS CONCERNING THE FUKUSHIMA DAIICHI NUCLEAR ACCIDENT Vol. 4 (2) (3) Reactions related to boron oxide (B 2 O 3 ) 5) metaboric acid orthoboric acid (4) (5) (6) Reactions related to decomposition of CH 4 6) (7) (8) Oxidation of Zr (9) where, the enthalpies of the reactions in formulas ( 1)-( 9) were calculated using the formation enthalpy at 1,500 K in the cited literature 7) .…”

Section: Chemical Reactionsmentioning

confidence: 99%

Effect of B₄C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions

Hidaka

2021

Insights Concerning the Fukushima Daiichi Nuclear Accident Vol. 4

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Boron carbide (B 4 C) used for BWR or EPR absorbers could cause phenomena that never occur in PWR with silver-indium-cadmium absorbers during a severe accident. B 4 C would undergo a eutectic interaction with stainless steel and enhance core melt relocation. Boron oxidation could increase H 2 generation, and the change of liberated carbon to CH 4 could enhance the generation of organic iodide (CH 3 I). HBO 2 generated during B 4 C oxidation could be changed to cesium borate (CsBO 2 ) by combining it with cesium. This may increase cesium deposition into the reactor coolant system. There could be differences in the configuration, surface area, and stainless-steel to B 4 C weight ratio between the B 4 C powder absorber and pellet absorber. The present task is to clarify the effect of these differences on melt progression, B 4 C oxidation, and the iodine or cesium source term. Advancement of this research field could contribute to further sophistication of prediction tools for melt progression and source terms of the Fukushima Accident, and the treatment of organic iodide formation in safety evaluation.

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Safety Assessment for Development of Severe Accident Management Guidelines Using In-House Code ‘Corves 2.0’ for KKNPP VVER-1000 Reactors

Chauhan,

Kumar,

Pandey

2024

Lecture Notes in Mechanical Engineering

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B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments

Cited by 18 publications

References 6 publications

Examination of ¹³¹I and ¹³⁷Cs releases during late phase of Fukushima Daiichi NPP accident by using ¹³¹I/¹³⁷Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Examination of ¹³¹I and ¹³⁷Cs releases during late phase of Fukushima Daiichi NPP accident by using ¹³¹I/¹³⁷Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Effect of B₄C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions

Safety Assessment for Development of Severe Accident Management Guidelines Using In-House Code ‘Corves 2.0’ for KKNPP VVER-1000 Reactors

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B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments

Cited by 18 publications

References 6 publications

Examination of 131I and 137Cs releases during late phase of Fukushima Daiichi NPP accident by using 131I/137Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Examination of 131I and 137Cs releases during late phase of Fukushima Daiichi NPP accident by using 131I/137Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Effect of B4C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions

Safety Assessment for Development of Severe Accident Management Guidelines Using In-House Code ‘Corves 2.0’ for KKNPP VVER-1000 Reactors

Contact Info

Product

Resources

About

Examination of ¹³¹I and ¹³⁷Cs releases during late phase of Fukushima Daiichi NPP accident by using ¹³¹I/¹³⁷Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Examination of ¹³¹I and ¹³⁷Cs releases during late phase of Fukushima Daiichi NPP accident by using ¹³¹I/¹³⁷Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Effect of B₄C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions