Japan Society of Civil Engineers 2019 Annual Meeting

Presentation information

第VII部門

放射性廃棄物 (3)

Thu. Sep 5, 2019 12:40 PM - 2:10 PM VII-2 (幸町南6号館 第1講義室)

座長:白瀬 光泰(原子力環境整備促進・資金管理センター)

[VII-147] Evaluation of gas release due to radiolysis from gamma-ray irradiated mortar under hardening process

*後藤 考裕1、北川 義人1、石川 俊介2、澤田 祥平2、紺谷 修2 (1. 原子力発電環境整備機構、2. 鹿島建設株式会社)

Keywords:Mortar, Hardening process, Gamma-ray irradiation, Radiolysis, Geological disposal, TRU waste

In order to evaluate the amount of hydrogen gas generation due to radiolysis at the TRU waste disposal facility during mortar filling around the waste package, gamma-ray irradiation test was conducted.Five cases of gamma-ray irradiation test and three cases of free water test, where the test parameters were gamma dose rate, heating temperature and presence or absence of retarder, were conducted using fresh mortar. G values evaluated from the irradiation test results were higher than one of bulk water and this is considered to be caused by the effect of interface between solid and water.

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