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Aono, Ryuji; Mitsukai, Akina; Tsuchida, Daiki; Konda, Miki; Haraga, Tomoko; Ishimori, Kenichiro; Kameo, Yutaka
JAEA-Data/Code 2023-002, 81 Pages, 2023/05
JAEA-Data-Code-2023-002.pdf:3.0MB
Radioactive wastes generated from nuclear research facilities in Japan Atomic Energy Agency are planning to be buried in the near surface disposal field as trench and pit. Therefore, it is required to establish the method to evaluate the radioactivity concentrations of radioactive wastes until the beginning of disposal. In order to contribute to this work, we collected and analyzed the samples generated from JRR-2, JRR-3 and Hot laboratory facilities. In this report, we summarized the radioactivity concentrations of 20 radionuclides (
H, 
C, 
Cl, 
Co, 
Ni, 
Sr, 
Nb, 
Tc, 
Ag, 
I, 
Cs, 
Eu, 
Eu, 
U, 
U, Pu, 
Pu, 
Pu, 
Am, 
Cm) which were obtained from radiochemical analysis of the samples in fiscal year 2020.
Nakayama, Masashi; Niunoya, Sumio*; Minamide, Masashi*
Genshiryoku Bakkuendo Kenkyu (CD-ROM), 23(1), p.25 - 30, 2016/06
In Japan, any high-level radioactive waste repository is to be constructed at over 300m depth below surface. Tunnel support is used for safety during the construction and operation, and shotcrete and concrete lining are used as the tunnel support. Concrete is a composite material comprised of aggregate, cement and various additives. Low alkaline cement has been developed for the long term stability of the barrier systems whose performance could be negatively affected by highly alkaline conditions arising due to cement used in a repository. Japan Atomic Energy Agency (JAEA) has developed a low alkaline cement, named as HFSC (Highly fly-ash contained silicafume cement), containing over 60wt% of silica-fume (SF) and coal ash (FA). JAEA is presently constructing an underground research laboratory (URL) at Horonobe for research and development in the geosciences and repository engineering technology. HFSC was used experimentally as the shotcrete material in construction of part of the 350m deep gallery in Horonobe URL in 2013. The objective of this experiment was to assess the performance of HFSC shotcrete in terms of mechanics, workability, durability, and so on. HFSC used in this experiment is composed of 40wt% OPC (Ordinary Portland Cement), 20wt% SF, and 40wt% FA. This composition was determined based on mechanical testing of various mixes of the above components. Because of the low OPC content, the strength of HFSC tends to be lower than that of OPC in normal concrete. The total length of tunnel constructed using HFSC shotcrete is about 112m at 350m deep drift. The workability of HFSC shotcrete was confirmed by this experimental construction. In this report, we present detailed results of the in-situ construction test.
Umino, Akira; Saito, Mitsuo; Kanazawa, Hiroyuki; Koya, Toshio; Okamoto, Hisato; Sekino, Hajime*; Nishino, Yasuharu
Dekomisshoningu Giho, (32), p.2 - 12, 2005/09
The Research Hot Laboratory (RHL) in Japan Atomic Research Institute (JAERI) was constructed in 1961, as the first one in JAPAN, to perform the examinations of irradiated fuels and materials. RHL with two floors and a basement consists of 10 heavy concrete cells, and 38 lead cells (20 lead cells at present). The RHL had been contributed to research program in JAERI. However, RHL is the one of target 'A middle-range decommissioning plan for the facility in Tokai Research Establishment' as the rationalization program for decrepit facilities in JAERI. Therefore, all PIEs had been finished in March 2003 and the dismantling works of hot cells have been started. The 18 lead cells had been dismantled. The examinations performed in RHL will be succeeded to the RFEF and the WASTEF. The partial area of RHL facility will be used for the temporary storage of un-irradiated fuel samples used for our previous research works and radioactive device generated in proton accelerator facility (called J-PARC).
Working Group for Investigation of Cause of Crack Initiation
JAERI-Tech 2003-060, 183 Pages, 2003/07
JAERI-Tech-2003-060.pdf:55.37MB
On December 10, 2002, the water leakage was found at the pressure instrumentation pipe attached to the exit pipe of No.1 charging pump of the purification system of a primary cooling system at JMTR, and the cracks were detected on the pressure instrumentation pipe by the visual observation. The Investigation Committee for Water Leakage from Instrumentation Pipe in JMTR was established and organized by specialists from inside and outside JAERI on December 16. In order to investigate the cause of crack initiation at the pressure instrumentation pipe, the Working Group was organized in the Department of JMTR. Visual inspection, fractgraphy test, metallographic observation and hardness test for the pressure instrumentation pipe and its weldment were carried out in the JMTR Hot Laboratory. This report summarized above data obtained by investigation on the cause of the crack initiation.
Department of JMTR
JAERI-Conf 99-009, p.393 - 0, 1999/09
no abstracts in English
Department of JMTR
JAERI-Review 98-004, 77 Pages, 1998/02
no abstracts in English
Department of JMTR
JAERI-M 93-016, 282 Pages, 1993/02
no abstracts in English
JAERI-M 91-150, 235 Pages, 1991/09
no abstracts in English
JAERI-M 90-166, 168 Pages, 1990/09
no abstracts in English
JAERI-M 82-017, 227 Pages, 1982/03
no abstracts in English
; ; ; *
Hoken Butsuri, 13(4), p.295 - 299, 1978/00
no abstracts in English
; ; Matsuura, Shojiro; ;
Nihon Genshiryoku Gakkai-Shi, 15(6), p.368 - 373, 1973/06
no abstracts in English
Onizawa, Kunio
no journal, ,
After TEPCO Fukushima-Daiichi NPS accident, new fuels and materials have been developed in the OECD/NEA member countries. The objective of the development is to have new fuels with enhanced accident tolerance, especially for severe accident conditions. For the new fuel development, similar to the conventional ones, many kinds of information are necessary to maintain the safety functions of the fuel. The fuel safety should be confirmed not only for severe accidents, but also for various conditions such as normal operation, design basis accidents, transportation and so on. Preparation of experimental databases with high reliability and analytical tools are also needed to confirm the safety of the new fuels. Therefore, test reactors and hot laboratories play important roles in the acquisition of in-reactor data which are the key information as the technical basis of safety judgement. In this presentation, safety requirements under various plant conditions which are considered in the new fuel development is explained. The importance of experiments using test reactors and laboratories for new fuel development is also explained including examples of JAEA facilities.
