Mechanical Engineering Journal
Online ISSN : 2187-9745
ISSN-L : 2187-9745
“Nuclear Power Saves the World!” and “Powering the World, One Atom at a Time”
Development of fission product chemistry database ECUME for the LWR severe accident
Shuhei MIWAKunihisa NAKAJIMANaoya MIYAHARAShunichiro NISHIOKAEriko SUZUKINaoki HORIGUCHIJiazhan LIUFaoulat MIRADJIJunpei IMOTOAfiqa MOHAMADGaku TAKASEHidetoshi KARASAWAMasahiko OSAKA
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2020 Volume 7 Issue 3 Pages 19-00537

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Abstract

We extended the first version of fission product (FP) chemistry database named ECUME (Effective Chemistry database of fission products Under Multiphase rEaction). The extended ECUME consists of three kinds of datasets: CRK (dataset for Chemical Reaction Kinetics), EM (Elemental Model set) and TD (ThermoDynamic dataset). The present ECUME is equipped with the CRK for the reaction of Cs-I-B-Mo-O-H system and Ru-N-O-H system in gas phase, the EM for the Cs chemical reaction with stainless steel (SS) (Cs chemisorption onto SS) and the TD for CsBO2 vapor species and solid Cs2Si4O9 and CsFeSiO4. A FP chemical reaction calculation in gas phase with the CRK of Cs-I-B-Mo-O-H system has shown the necessity of consideration of chemical reaction kinetics for more accurate estimation of Cs and I release amount into environment. The EM for Cs chemisorption has successfully achieved more accurate estimation of Cs distribution in a reactor by reproducing the effects of CsOH vapor concentration in gas phase and Si content in SS which were not considered by the existing model. The high quality vapor pressure data for CsBO2 vapor were evaluated based on the result of a high temperature mass spectrometry. Cesium species at high temperature can be estimated by the thermodynamic data with high reliability. Thermodynamic data for solid Cs2Si4O9 and CsFeSiO4 were successfully evaluated by the experiment and ab-initio based methodology, respectively. These results have shown the validity and importance of the ECUME application for the more accurate evaluation of FP chemistry during transportation in a reactor under a LWR severe accident.

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© 2020 The Japan Society of Mechanical Engineers
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