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Nakayama, Masashi
JAEA-Data/Code 2020-009, 98 Pages, 2020/09
JAEA-Data-Code-2020-009.pdf:6.06MB
JAEA-Data-Code-2020-009-appendix1(DVD-ROM).zip:172.11MBJAEA-Data-Code-2020-009-appendix2-1(DVD-ROM).zip:468.85MBJAEA-Data-Code-2020-009-appendix2-2(DVD-ROM).zip:102.94MBJAEA-Data-Code-2020-009-appendix2-3(DVD-ROM).zip:141.88MBJAEA-Data-Code-2020-009-appendix2-4(DVD-ROM).zip:141.6MB
Japan Atomic Energy Agency (JAEA) has developed a low alkaline cement, named as HFSC (Highly Fly-ash contained Silicafume Cement), in order to decrease the effect on geological environment of cementitious material. HFSC was used experimentally as the shotcrete (140m, 250m and 350m depth gallery) and lining concrete (GL-374m to GL-380m of east access shaft) in construction part of Horonobe URL. In order to evaluate the effect of HFSC on the surrounding rock and groundwater, concrete and rock cores were periodically sampled from the site where the in-situ construction test was conducted, and various analyzes were conducted. Ordinary Portland Cement (OPC) was used for part of 140m depth gallery, and the same analysis as HFSC was conducted, in order to compare the effect of OPC and HFSC. This report summarizes the results of analyzes conducted on core samples from 2009 to 2018.
C from irradiated graphite materials, 1; Oxidation behaviors and the changes in pore structure of Q1 and IG-110 graphite due to the air reaction (Joint research)Fujii, Kimio
JAERI-Tech 2005-048, 108 Pages, 2005/09
JAERI-Tech-2005-048.pdf:25.05MB
The graphite-moderated power reactor was shut down in 1998 and its decommissioning program is being planned. Various graphites are used in the core of magnox-type reactors and HTTR as core-support structural materials and moderating materials of fast neutrons. For the nuclear graphite disposal, it is necessary to determine especially the treatment of long-lived nuclides, such as C which are generated in the graphite components during reactor operation. As a research, which solves the problem of the C concentration, the cooperative research is concluded between JAERI and Japan Nuclear Power Corp. in 1999, and the research for the basic data acquisition has been advanced up to the present. To find the optimum conditions for C reduction, basic data on oxidation reaction and the structure of graphite materials are indispensable. In the present experiment, we measure the air oxidation characteristics in the temperature range 450
800
C in Quality1 graphite and IG-110 graphite. Changes in pore diameter and pore size distribution due to air oxidation are discussed.