Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Hayashida, Kazuki; Munemoto, Takashi; Aosai, Daisuke*; Inui, Michiharu*; Iwatsuki, Teruki
JAEA-Data/Code 2016-001, 64 Pages, 2016/06
JAEA-Data-Code-2016-001.pdf:3.19MB
Japan Atomic Energy Agency has been investigating groundwater chemistry to understand the effect on excavating and maintenance of underground facilities as part of the Mizunami Underground Research Laboratory (MIU) Project in Mizunami, Gifu, Japan. In this report, we compiled data of groundwater chemistry obtained at the MIU in the fiscal year 2014. In terms of ensuring traceability of data, basic information (e.g. sampling location, sampling time, sampling method, analytical method) and methodology for quality control are described.
Yokoi, Shinobu*; Kamishima, Yoshio*; Sadahiro, Daisuke*; Takaya, Shigeru
JAEA-Data/Code 2016-002, 38 Pages, 2016/07
JAEA-Data-Code-2016-002.pdf:1.51MB
Many efforts have been made to implement the System Based Code concept aiming at optimizing margins dispersed in existing codes and standards. Failure probability calculated based on statistical information such as a type of probability distribution, mean (or median) and variance (or standard deviation) for random variables is expected to be a promising quantitative index for margin optimization. Statistical information on material strength, which is also required to calculate the failure probability, has been already reported in JAEA-Data/Code 2015-002 "Structural Properties of Material Strength for Reliability Evaluation of Components of Fast Reactors -Austenitic Stainless Steels-" whereas others have not been identified yet. This report provides methodologies and basic ideas to determine statistical parameters of other random variables, especially variable loads, necessary for reliability evaluation.
Sakurai, Akitaka; Aoyagi, Kazuhei
JAEA-Data/Code 2016-003, 84 Pages, 2016/07
JAEA-Data-Code-2016-003.pdf:6.42MB
JAEA-Data-Code-2016-003-appendix(DVD-ROM).zip:184.29MB
The Horonobe Underground Research Laboratory (URL) Project has being pursued by Japan Atomic Energy Agency (JAEA) to enhance the reliability of relevant disposal technologies through investigations of the deep geological environment within the host sedimentary formations at Horonobe, northern Hokkaido. The URL project consists of two major research areas, "Geoscientific Research" and "R&D on Geological Disposal Technologies", and proceeds in three overlapping phases, "Phase I: Surface-based investigations", "Phase II: Investigations during tunnel excavation" and "Phase III: Investigations in the underground facilities", over a period of around 20 years. The Phase I geoscientific research was carried out from March 2001 to March 2006 in parallel with design and execution scheme on URL facilities. In addition, identifying key issues that need to be addressed in the Phase II/III investigations was planned. At the beginning of the Phase II investigations, investigation reports related to measurement plan and observational construction program on shaft and drift excavation were published. The observational construction program summarizes the followings from the results of the Phase I investigations: measurements for safety and reasonable constructions, enhancement of shaft design and construction technologies and evaluation of appropriateness for the deep geological environment model estimated before shaft excavation. Currently, Phase III investigation related to geological disposal in underground facilities has been conducting. Also, measurement for consideration of long-term stability of the tunnel has been continued. This report summarizes the measurements data acquired at the West Shaft in 2014 fiscal year for the purpose of the basic data for carrying out the Observational Construction Program.
Takeda, Takeshi
JAEA-Data/Code 2016-004, 59 Pages, 2016/07
JAEA-Data-Code-2016-004.pdf:3.34MB
The TR-LF-07 test simulated a loss-of-feedwater transient in a PWR. A SI signal was generated when steam generator (SG) secondary-side collapsed liquid level decreased to 3 m. Primary depressurization was initiated by fully opening a power-operated relief valve (PORV) of pressurizer (PZR) 30 min after the SI signal. High pressure injection (HPI) system was started in loop with PZR 12 s after the SI signal, while it was initiated in loop without PZR when the primary pressure decreased to 10.7 MPa. The primary and SG secondary pressures were kept almost constant because of cycle opening of the PZR PORV and SG relief valves. The PZR liquid level began to drop steeply following the PORV full opening, which caused liquid level formation at the hot leg. The primary pressure became lower than the SG secondary pressure, which resulted in the actuation of accumulator (ACC) system in both loops. The primary feed-and-bleed operation was effective to core cooling because of no core uncovery.
Nakayama, Masashi; Ono, Hirokazu; Nakayama, Mariko*; Kobayashi, Masato*
JAEA-Data/Code 2016-005, 55 Pages, 2016/07
JAEA-Data-Code-2016-005.pdf:11.32MBJAEA-Data-Code-2016-005-appendix(CD-ROM).zip:32.68MB
The Horonobe URL Project has being pursued by JAEA to enhance the reliability of relevant disposal technologies through investigations of the deep geological environment within the host sedimentary formation at Horonobe, northern Hokkaido. The Project consists of two major research areas, "Geoscientific Research" and "Research and Development on Geological Disposal Technologies", and proceeds in three overlapping phases, "Phase I: Surface-based investigations", "Phase II: Investigations during tunnel excavation" and "Phase III: Investigations in the underground facilities". Phase III investigation was started in 2010 fiscal year. The in-situ experiment for performance confirmation of engineered barrier system (EBS experiment) had been prepared from 2013 to 2014 fiscal year at GL-350m gallery, and heating by electric heater in simulated overpack had started in January, 2015. One of objectives of the experiment is acquiring data concerned with Thermal-Hydrological-Mechanical-Chemical (THMC) coupled behavior. These data will be used in order to confirm the performance of engineered barrier system. This report summarizes the measurement data acquired from the EBS experiment from December, 2014 to March, 2016.
Hama, Katsuhiro
JAEA-Data/Code 2016-006, 23 Pages, 2016/07
JAEA-Data-Code-2016-006.pdf:1.6MB
The Mizunami Underground Research Laboratory project is being pursued by the Japan Atomic Energy Agency to enhance the reliability of relevant disposal technologies through investigations of the deep geological environment within the host crystalline rock at Mizunami City in Gifu Prefecture, central Japan. The project proceeds in three overlapping phases, Surface-based investigation Phase, Construction Phase and Operation Phase. The MIU Project has been ongoing the Phase III. As a part of the Phase III investigation, evaluation of mass transport property using natural Uranium-series and Thorium-series nuclides has been carried out. In this report, the compilation of existing data and preliminary evaluation was carried out.
Imai, Yoshiyuki; Sato, Hiroyuki; Nomoto, Yasunobu; Yan, X.
JAEA-Data/Code 2016-007, 27 Pages, 2016/08
JAEA-Data-Code-2016-007.pdf:3.65MB
This report provides design database for helium gas turbine for HTGR. The design details for secondary helium cooling system and helium gas turbine in a heat application system to be coupled to the HTTR are described. In addition, experimental data for fission product isotope diffusion through turbine blade alloy is compiled.
Akimoto, Hajime; Sugawara, Takanori
JAEA-Data/Code 2016-008, 87 Pages, 2016/09
JAEA-Data-Code-2016-008.pdf:15.62MB
Thermal hydraulic behavior in a lead-bismuth cooled accelerator driven system (ADS) is analyzed under normal operation condition. Input data for the ADS version of J-TRAC code have been constructed to integrate the conceptual design. The core part of the ADS is modeled in detail to evaluate the core radial power profile effect on the core cooling. As the result of the analyses, the followings are found; (1) Both maximum clad temperature and fuel temperature are below the design limits. (2) The radial power profile has little effect on the coolant flow distribution among fuel assemblies. (3) The radial power profile has little effect on the heat transfer coefficients along fuel rods. (4) The thermal hydraulic behaviors along four steam generators are identical. The thermal hydraulic behaviors along two pumps are also identical. A fast running input data is developed by the simplification of the detailed input data based on the findings mentioned above.
Ishibashi, Masayuki; Sasao, Eiji
JAEA-Data/Code 2016-009, 10 Pages, 2016/08
JAEA-Data-Code-2016-009.pdf:3.65MBJAEA-Data-Code-2016-009-appendix(CD-ROM).zip:0.64MB
Japan Atomic Energy Agency (JAEA) Tono Geoscience Center (TGC) is pursuing a geoscientific research in crystalline rock environment in order to construct scientific and technological basis for the geological disposal of High-level Radioactive Waste. This report compiles the information of the fractures in the Toki Granite, central Japan, obtained by Borehole TV observations of borehole investigations, drilled in underground facility.
Ueki, Tadamasa; Tanabe, Hiroaki*; Niwa, Masakazu; Ishimaru, Tsuneari; Shimada, Koji
JAEA-Data/Code 2016-010, 292 Pages, 2016/09
JAEA-Data-Code-2016-010.pdf:76.12MB
Occurrence of recent activity of faults is often evaluated based on displacements of subsurface sediments covering the faults. However, this evaluation is not applicable for faults that occur where subsurface sediments are not found. In this study, mesoscopic description in a field, microscopic observation using thin sections, chemical composition mapping for polished slabs, X-ray diffraction analysis, particle size distribution analysis, and detailed analysis for quartz fragments (scanning electron microscopy and measurement of electron spin resonance signals) were carried out for clay veins in order to contribute a development of evaluation of fault activity. This Data/Code reports the results of these observation and analyses.
Seno, Yasuhiro*; Nakayama, Masashi; Sugita, Yutaka; Tanai, Kenji; Fujita, Tomoo
JAEA-Data/Code 2016-011, 164 Pages, 2016/11
JAEA-Data-Code-2016-011.pdf:8.45MBJAEA-Data-Code-2016-011-appendix(CD-ROM).zip:0.1MB
The cementitious materials are used as candidate materials for the tunnel support of the deep geological repository of high-level radioactive wastes (HLW).Generally the pH of leachate from concrete mixed Ordinary Portland Cement (OPC) shows a range of 12 to 13. The barrier function of bentonite used as a buffer material and that of host rock might be damaged by the high alkaline leachate from cementitious materials. Therefore, low alkalinity that does not damage each barrier function is necessary for cementitious materials used for the tunnel support system of the HLW geological repository. JAEA has developed a low alkaline cement named as HFSC (Highly Fly-ash contained Silicafume Cement) which the pH of the cement leachate could lower approximately 11. We have confirmed the applicability of HFSC for the tunnel support materials, by using experimentally as the shotcreting materials to the part of gallery wall at 140m, 250m and 350m depth in Horonobe Underground Research Laboratory. And moreover, HFSC has been used as the cast-in-place concrete for the shaft lining concrete at the depth of 374m-380m. This Data/Code summarized the past HFSC mix proportion test results about the fresh concrete properties and hardened concrete properties, in order to offer the information as a reference for selecting the mix proportion of HFSC concrete adopted to the disposal galleries et al. in the future.
Onoe, Hironori; Takeuchi, Ryuji
JAEA-Data/Code 2016-012, 46 Pages, 2016/11
JAEA-Data-Code-2016-012.pdf:8.52MB
This report summarize the results of the single borehole hydraulic tests of 151 sections were carried out at the -300 m Stage and the -500 m Stage of the Mizunami Underground Research Laboratory from FY 2012 to FY 2015. The details of each test (test interval depth, geology, etc.) as well as the interpreted hydraulic parameters and analytical method used are presented in this report. And, the previous results of the single borehole hydraulic tests were carried out in Regional Hydrogeological Study Project and Mizunami Underground Research Laboratory Project before FY 2012 is summarized in this report.
Manabe, Kentaro; Sato, Kaoru; Takahashi, Fumiaki
JAEA-Data/Code 2016-013, 48 Pages, 2016/12
JAEA-Data-Code-2016-013.pdf:1.3MBJAEA-Data-Code-2016-013-appendix(CD-ROM).zip:0.47MB
In the 2007 Recommendations of the International Commission on Radiological Protection (ICRP), an effective dose is defined as a sum of equivalent doses which are calculated by using male and female reference phantoms based on Caucasian physiological data and averaged over the sexes by tissue weighting factors. Specific absorbed fractions (SAFs), which are essential for internal dosimetry, depend on the body weight and organ masses of phantoms. Then, the dose coefficients, which are committed effective doses per unit intake of radionuclides, developed by ICRP on the basis of the 2007 Recommendations reflect the physical characteristics of Caucasians and are averaged over the sexes. Meanwhile, the physiques of adult Japanese are generally smaller than those of adult Caucasians, and organ masses are also different from each other. Knowledge of the influence of race differences on dose coefficients is important to apply the sex averaged dose coefficients of ICRP to the Japanese system of radiation protection. In this study, SAFs for 25 kinds of mono-energetic electrons and photons ranging from 10 keV to 10 MeV were calculated about the combinations of 67 source regions and 42 target organs using the average adult Japanese female phantom, JF-103, incorporated with a general purpose radiation transport code, MCNPX 2.6.0. The data of this report and the previously published data of JM-103 are applicable to evaluate sex-specific and sex-averaged dose coefficients reflecting the physical characteristics of the average adult Japanese for intakes of all radionuclides not to emit other than photons and electrons.
Katata, Genki; Ota, Masakazu
JAEA-Data/Code 2016-014, 35 Pages, 2017/01
JAEA-Data-Code-2016-014.pdf:1.64MB
In order to predict the impact of atmospheric pollutants (gases and aerosols) to the terrestrial ecosystem, new schemes for calculating the processes of dry deposition of gases and aerosols, and water and carbon cycles in terrestrial ecosystems were implemented in the one-dimensional atmosphere-SOiL-VEGetation model, SOLVEG. We made performance tests at various vegetation areas to validate the newly developed schemes. In this report, the detail in each modeled process is described with an instruction how to use the modified SOLVEG. The framework of "terrestrial ecosystem model" was developed for investigation of a change in water, energy, and carbon cycles associated with global warming and air pollution and its impact on terrestrial ecosystems.
Nomura, Katsuhiro; Tanikawa, Shinichi*; Amamiya, Hiroki; Yasue, Kenichi
JAEA-Data/Code 2016-015, 49 Pages, 2017/03
JAEA-Data-Code-2016-015.pdf:2.88MB
The uplift of the last hundred thousand years in the Japanese Islands has been acquired mainly using marine and river terraces. We arranged information regarding the uplift in a table. This data is one of the useful information for the development of the investigation technology of uplift and for the research of the landform evolution in Japanese islands.
Takahara, Shogo; Watanabe, Masatoshi; Oguri, Tomomi; Kimura, Masanori; Hirouchi, Jun; Munakata, Masahiro; Homma, Toshimitsu
JAEA-Data/Code 2016-016, 65 Pages, 2017/02
JAEA-Data-Code-2016-016.pdf:2.32MB
We surveyed on structural and material data on 22 facilities which are listed in local disaster management plan in Matsue city. These facilities can be divided into educational facilities, communal facilities and gymnastic hall. Height and floor-area of rooms, as well as window-area were collected as the structural data. We also collected information on constructional materials, and density of those. In addition, mass-thicknesses of the constructional materials were evaluated based on our surveys, and compared to the previous studies which were made in Japan, U.S., and European countries. Consequently, it was found that there is no significant difference of mass-thickness of constructional materials between the results of our surveys and the previous studies. However, for gymnastic hall, since thin metal plates are used for roofs, we can point out that the mass-thickness of roofs are much lower than those for other concrete facilities and clay tile roofing wooden houses.
Haraga, Tomoko; Tobita, Minoru*; Takahashi, Shigemi*; Seki, Kotaro*; Izumo, Sari; Shimomura, Yusuke; Ishimori, Kenichiro; Kameo, Yutaka
JAEA-Data/Code 2016-017, 53 Pages, 2017/02
JAEA-Data-Code-2016-017.pdf:3.17MB
Fugen Nuclear Power Station was shut down and now is under decommissioning. Many radioactivity concentration data of dismantled materials have to be accumulated to calculate the scaling factors of radioactive wastes and to verify that the cleared dismantled materials conform to the clearance levels. A simple and rapid radioactivity determination method for radioactive waste samples was developed by Department of Decommissioning and Waste Management. For its demonstration, the simple and rapid radioactivity determination method was applied to metal samples, which were taken from dismantled pipes in contact with heavy water or carbon dioxide gas of Fugen. This report summarizes the radioactivity data obtained from the analysis of those samples.
Nagaya, Yasunobu; Okumura, Keisuke; Sakurai, Takeshi; Mori, Takamasa
JAEA-Data/Code 2016-018, 421 Pages, 2017/03
JAEA-Data-Code-2016-018.pdf:3.89MBJAEA-Data-Code-2016-018-appendix(CD-ROM).zip:4.02MBJAEA-Data-Code-2016-018-hyperlink.zip:1.94MB
In order to realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two Monte Carlo codes MVP (continuous-energy method) and GMVP (multigroup method) have been developed at Japan Atomic Energy Agency. The codes have adopted a vectorized algorithm and have been developed for vector-type supercomputers. They also support parallel processing with a standard parallelization library MPI and thus a speed-up of Monte Carlo calculations can be achieved on general computing platforms. The first and second versions of the codes were released in 1994 and 2005, respectively. They have been extensively improved and new capabilities have been implemented. The major improvements and new capabilities are as follows: (1) perturbation calculation for effective multiplication factor, (2) exact resonant elastic scattering model, (3) calculation of reactor kinetics parameters, (4) photo-nuclear model, (5) simulation of delayed neutrons, (6) generation of group constants, etc. This report describes the physical model, geometry description method used in the codes, new capabilities and input instructions.
Nagaya, Yasunobu; Okumura, Keisuke; Sakurai, Takeshi; Mori, Takamasa
JAEA-Data/Code 2016-019, 450 Pages, 2017/03
JAEA-Data-Code-2016-019.pdf:4.43MBJAEA-Data-Code-2016-019-hyperlink.zip:2.36MB
In order to realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two Monte Carlo codes MVP (continuous-energy method) and GMVP (multigroup method) have been developed at Japan Atomic Energy Agency. The codes have adopted a vectorized algorithm and have been developed for vector-type supercomputers. They also support parallel processing with a standard parallelization library MPI and thus a speed-up of Monte Carlo calculations can be achieved on general computing platforms. The first and second versions of the codes were released in 1994 and 2005, respectively. They have been extensively improved and new capabilities have been implemented. The major improvements and new capabilities are as follows: (1) perturbation calculation for effective multiplication factor, (2) exact resonant elastic scattering model, (3) calculation of reactor kinetics parameters, (4) photo-nuclear model, (5) simulation of delayed neutrons, (6) generation of group constants, etc. This report describes the physical model, geometry description method used in the codes, new capabilities and input instructions.
Takai, Shizuka; Takayama, Hideki*; Takeda, Seiji
JAEA-Data/Code 2016-020, 40 Pages, 2017/03
JAEA-Data-Code-2016-020.pdf:2.42MB
In this report, another group of scenarios for occurrence of earthquake at construction stage, operation stage and closure stage of disposal facility was presented. At first, we compiled information about damage cases of tunnel by earthquake and analyzed conditions for occurrence of damage. Base on this result and the previous report, information of influence of the accidents and human factors on safety functions and information of FEP about THMC variation, we specified events to be considered, which occur by earthquake and influence engineering barriers, natural barriers and long-term safety after closure stage of disposal facility. We compiled influence of the events on safety functions after closure stage of disposal and showed the chains of the influence on long-term safety as scenarios. These results were integrated as a database that could support development of scenarios caused by application of engineering technologies to geological disposal.
Miyakawa, Kazuya; Tamamura, Shuji*; Nakata, Kotaro*; Hasegawa, Takuma*
JAEA-Data/Code 2016-021, 60 Pages, 2017/03
JAEA-Data-Code-2016-021.pdf:3.87MBJAEA-Data-Code-2016-021-appendix(CD-ROM).zip:0.45MB
The Japan Atomic Energy Agency has been involved in ongoing research in the Horonobe area for the purposes of geoscientific research, and research and development (R&D) on technologies to be used for the geological disposal of high-level radioactive waste. The chemistry of groundwater and dissolved gas from deep boreholes has been obtained since H13 fiscal year for R&D on technologies related to geological characterization. Horonobe Research Institute for the Subsurface Environment (H-RISE) has investigated a resources development on promoting effective use of coal bed buried in Hokkaido including the Horonobe area using microbial communities. The data of dissolved gas from the Horonobe groundwater have also been obtained along with the microbiological research by H-RISE. Central Research Institute of Electric Power Industry (CRIEPI) has conducted R&D on technology of groundwater geochronology which is one of technologies to be used for the geological disposal, and noble gas data from the Horonobe groundwater have been obtained by CRIEPI. This report shows a data set which comprises gas data obtained from the Horonobe underground research project during the period from H13 fiscal year to H27 fiscal year.
Aoyagi, Kazuhei; Sakurai, Akitaka; Niunoya, Sumio*
JAEA-Data/Code 2016-022, 91 Pages, 2017/03
JAEA-Data-Code-2016-022.pdf:7.3MBJAEA-Data-Code-2016-022-appendix(CD-ROM).zip:232.99MB
The objective of this report is to investigate the three dimensional stress state in the 350 m Loop Gallery (East) at the Horonobe Underground Research Laboratory. For the measurement, three boreholes, which are 17.0 m in length, were drilled. Hydraulic fracturing was applied as a stress measurement method. For the analysis, shut-in pressure of a transverse fractures, reopening pressure of longitudinal fractures and stress condition causing borehole breakouts were integrated into the equation; then stress state was calculated by inversion technique. As a result, considering the stress condition causing breakouts, the value of the maximum principal stress was 3.73 MPa, which is much smaller than the overburden pressure (about 6.0 MPa). The orientation of the maximum horizontal stress is almost vertical. The stress state is normal faulting.