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JAEA Reports

Study of hydrogeology in the Mizunami Underground Research Laboratory Project; Numerical prediction of recovery behavior of groundwater environment during groundwater filling test and underground facility closure

Onoe, Hironori; Kimura, Hitoshi*

JAEA-Research 2019-001, 57 Pages, 2019/08

JAEA-Research-2019-001.pdf:10.03MB

In this study, predictive simulations were conducted in order to understand recovery behavior of groundwater environment during groundwater filling test and underground facility closure. As a result of predictive simulations of groundwater filling test, difference of groundwater environment changes around the closure test drift according to groundwater filling volume was confirmed quantitatively. As a result of the simulations, groundwater environment changes at 10 years after underground facility closure could be estimated. And, it was shown that up-corning of deep saline water through drift and shaft was occurred if hydraulic conductivity of backfill material is higher than host rock.

Journal Articles

Estimation on the change of the condition of the impervious plug during groundwater recovery experiment

Matsui, Hiroya; Mikake, Shinichiro; Ikeda, Koki; Tsutsue, Jiyun

Dai-46-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koenshu (CD-ROM), p.286 - 291, 2019/01

Japan Nuclear Energy Agency (JAEA) has been conducting the groundwater recovery experiment to develop a methodology to estimate the geological environment recovery after closure of the drift at GL-500m in Mizunami Underground Research Laboratory, Japan. For the experiment, an impervious concrete plug was constructed to maintain a recovered water pressure and its functions were assessed based on the monitoring results and interpretation of several kinds of measurements performed inside and outside of the plug during groundwater recovery test. This report summarized the change of the condition of the plug due to groundwater recovery estimated based on the different kinds of monitoring data.

Journal Articles

Transition of near surface resistivity of tunnel wall during drift closure test

Ozaki, Yusuke; Ishibashi, Masayuki; Matsushita, Tomoaki*; Masumoto, Kazuhiko*; Imasato, Takehiko*

Proceedings of 13th SEGJ International Symposium (USB Flash Drive), 4 Pages, 2018/11

In the Mizunami Underground Research Laboratory, Groundwater REcoverty Experiment in Tunnel (GREET) is performed to understanding the recovery process of geological environment after the closure of drift. In this experiment, we performed 2D electrical resistivity surveys three times. First survey was performed before the closure of test drift. Second and third surveys were performed after the closure test. The first survey detected two layers conformation that consists of conductive and resistive zones at shallower and deeper part from the drift surface, respectively. These layers correspond to the shotcrete and host rock, respectively. Second and third measurements show that the conductive zone expanded to deeper resistive part while the shallower conductive part did not change. We concluded that we captured the saturation process of dried fractures near the drift wall by closure of drift as an electrical resistivity response.

JAEA Reports

Backfilling test in drilling pits as part of Groundwater REcovery Experiment in Tunnel (GREET) Project

Takayasu, Kentaro; Onuki, Kenji*; Kawamoto, Koji*; Takayama, Yusuke; Mikake, Shinichiro; Sato, Toshinori; Onoe, Hironori; Takeuchi, Ryuji

JAEA-Technology 2017-011, 61 Pages, 2017/06

JAEA-Technology-2017-011.pdf:9.15MB

The Groundwater REcovery Experiment in Tunnel (GREET) was put into effect as development of drift backfilling technologies. This test was conducted by making the Closure Test Drift (CTD) recovered with water after carrying out a plug around 40m distance from northern edge face of horizontal tunnel of depth 500m, for the purpose of investigation of recovering process of rock mass and groundwater under the influence of excavation of tunnel. This report presents the efforts of backfilling investigation using bentonite composite soil and execution of backfilling into borehole pits excavated in the CTD which were carried out in fiscal 2014 as a part of GREET, and succeeding observation results inside pits from September 2014 to March 2016.

JAEA Reports

Study on engineering technologies in the Mizunami Underground Research Laboratory (FY 2013); Development of recovery and mitigation technology on excavation damage (Contract research)

Fukaya, Masaaki*; Hata, Koji*; Akiyoshi, Kenji*; Sato, Shin*; Takeda, Yoshinori*; Miura, Norihiko*; Uyama, Masao*; Kaneda, Tsutomu*; Ueda, Tadashi*; Toda, Akiko*; et al.

JAEA-Technology 2014-040, 199 Pages, 2015/03

JAEA-Technology-2014-040.pdf:37.2MB

The researches on engineering technology in the Mizunami Underground Research Laboratory (MIU) project consists of (1) development of design and construction planning technologies, (2) development of construction technology, (3) development of countermeasure technology, (4) development of technology for security, and (5) development of technologies for restoration and/or reduction of the excavation damage. The researches on engineering technology such as verification of the initial design were being conducted by using data measured during construction as a part of the second phase of the MIU plan. Examination about the plug for reflood test in the GL-500m Access/Research Gallery-North as part of the development of technologies for restoration and/or reduction of excavation damage were carried out. Specifically, Literature survey was carried out about the plug, based on the result of literature survey, examination of the design condition, design of the plug and rock stability using numerical simulation, selection of materials for major parts, and grouting for water inflow from between rock and plug, were carried out in this study.

JAEA Reports

A Research program for numerical experiments on coupled thermo-hydro-mechanical and chemical processes

Ito, Akira; Kawakami, Susumu; Yui, Mikazu

JNC-TN8400 2001-028, 38 Pages, 2002/01

JNC-TN8400-2001-028.pdf:2.35MB

In a repository for high-level radioactive waste, coupled thermo -hydro -mechanical and chemical (THMC) processes will ocurr, involving the interactive processes between radioactive decay heat from the vitrified waste, infiltration of groundwater, swelling pressure generation and chemical evolution of the buffer material and porewater chemistry. In this program, numerical experiment system for the coupled THMC processes will be developed in order to predict the long-term performance of the near-field (engineered barrier and host rock) for various geological environments. The simulation code development has been started in FY 2001 and three development steps are planned, because (1)development will be continued for some years, (2)feasibility of numerical experiment have to be confirmed by using existing tools. This report presents the following items of the simulation code development for the coupled THMC processes. (1)First step of the simulation code development (2)Mass transport passways in compacted bentonite (3)Parallelization of the simulation code

JAEA Reports

None

*

JNC-TJ7400 2000-015, 203 Pages, 2000/08

JNC-TJ7400-2000-015.pdf:6.07MB

no abstracts in English

JAEA Reports

Evaluation of Coupled Thermo-Hydro-Mechanical Phenomena in the Near Field for Geological Diaposal of High-Level Radioactive waste

Chijimatsu, Masakazu*; Fujita, Tomo; Sugita, Yutaka; Taniguchi, Wataru

JNC-TN8400 2000-008, 339 Pages, 2000/01

JNC-TN8400-2000-008.pdf:15.57MB

Geological disposal of high-level radioactive waste (HLW) in Japan is based on a multibarrier system composed of engineered and natural barriers. The engineered barriers are composed of vitrified waste confined within a canister, overpack and buffer material. Highly compacted bentonite clay is considered one of the most promising candidate buffer material mainly because of its low hydraunc conductivity and high adsorption capacity of radionuclides. In a repository for HLW, complex thermal, hydraulic and mechanical (T-H-M) phenomena will take place, involving the interactive processes between radioactive decay heat from the vitrified waste, infiltration of ground water and stress generation due to the earth pressure, the thermal loading and the swelling pressure of the buffer material. In order to evaluate the performance of the buffer material, the coupled T-H-M behaviors within the compacted bentonite have to be modelled. Before establishing a fully coupled T-H-M model, the mechanism of each single Phenomenon or partially coupled phenomena should be identified. Furthermore, in order to evaluate the coupled T-H-M phenomena, the analysis model was developed physically and numerically and the adequacy and the applicability was tested though the engineered scale laboratory test and in-situ test. In this report, the investigative results for the development of coupled T-H-M model were described. This report consists of eight chapters. In Chapter l, the necessity of coupled T-H-M model in the geological disposal project of the high-level radioactive waste was described. In Chapter 2, the laboratory test results of the rock sample and the buffer material for the coupled T-H-M analysis were shown. nle rock samples were obtained from the in-situ experimental site at Kamaishi mine. As the buffer material, bentonite clay (Kunigel V1 and Kunigel OT-9607) and bentonite-sand mixture were used. In Chapter 3, in-situ tests to obtain the rock property were shown. As ...

JAEA Reports

None

JNC-TJ1400 99-038, 83 Pages, 1999/02

JNC-TJ1400-99-038.pdf:4.96MB

no abstracts in English

JAEA Reports

Study on thermal-hydraulics during a PWR reflood phase

Iguchi, Tadashi

JAERI-Research 98-054, 216 Pages, 1998/10

JAERI-Research-98-054.pdf:7.94MB

no abstracts in English

JAEA Reports

None

*

PNC-TJ1559 98-002, 260 Pages, 1998/03

PNC-TJ1559-98-002.pdf:6.08MB

no abstracts in English

JAEA Reports

None

Yamaguchi, Takashi

PNC-TN1410 97-030, 107 Pages, 1997/08

PNC-TN1410-97-030.pdf:1.98MB

no abstracts in English

JAEA Reports

None

Yamaguchi, Takashi

PNC-TN1410 97-029, 65 Pages, 1997/08

PNC-TN1410-97-029.pdf:1.26MB

no abstracts in English

Journal Articles

Experimental study on difference in reflood core heat transfer among CCTF, FLECHT-SET and predicted with FLECHT correlation

Okubo, Tsutomu; Iguchi, Tadashi; Murao, Yoshio

Journal of Nuclear Science and Technology, 31(8), p.839 - 849, 1994/08

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

Shibata, Masahiro; Yamagata, Junji*; Suzuki, Hideaki*

PNC-TN8410 92-169, 64 Pages, 1992/08

PNC-TN8410-92-169.pdf:1.06MB

None

Journal Articles

Hydrogen generation during reflooding of degraded core as an accident management measure

Hidaka, Akihide; Sugimoto, Jun; Soda, Kunihisa

EUR-14039-EN, p.28 - 36, 1992/00

no abstracts in English

Journal Articles

On the numerical characteristics of reflood model with use of moving mesh system

Watanabe, Tadashi; Kukita, Yutaka

Numerical Modelling of Basic Heat Transfer Phenomena in Nuclear Systems, p.25 - 30, 1991/00

no abstracts in English

JAEA Reports

Sensitivity analyses on reflooding effect on the TMI-2 accident by the SCDAP code

Hidaka, Akihide; Sugimoto, Jun; *; Soda, Kunihisa

JAERI-M 89-213, 87 Pages, 1989/12

JAERI-M-89-213.pdf:1.66MB

no abstracts in English

Journal Articles

Experimental study of ECC water injection rate effects on reflood phase of PWR-LOCA

; Murao, Yoshio

Journal of Nuclear Science and Technology, 22(2), p.93 - 108, 1985/00

 Times Cited Count:4 Percentile:44.64(Nuclear Science & Technology)

no abstracts in English

43 (Records 1-20 displayed on this page)