Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Takahara, Shogo; Hidaka, Akihide; Ogino, Takashi*
JAEA-Data/Code 2015-001, 65 Pages, 2015/03
JAEA-Data-Code-2015-001.pdf:10.74MB
HEINPUT code is one of the preprocessor for probabilistic accident consequence assessment code OSCAAR, and estimates the risk of incidence and death due to radiation induced cancers. HEINPUT code currently uses two models developed by U.S. Nuclear Regulatory Commission (USNRC, 1985; 1993) and U.S. Environmental Protection Agency (EPA, 1994). In this report, the code was improved to enable to make calculation using the new EPA model. In addition, in order to reduce user's burden, we developed input data generator which can provide the input data for three estimation models implemented in HEINPUT-GUI based on the statistical information published.
Takaya, Shigeru; Sasaki, Naoto*; Tomobe, Masato*
JAEA-Data/Code 2015-002, 54 Pages, 2015/03
JAEA-Data-Code-2015-002.pdf:25.53MB
Many efforts have been made to implement the System Based Code concept of which objective is to optimize margins dispersed in several codes and standards. Failure probability is expected to be a promising quantitative index for optimization of margins, and statistical information for random variables is needed to evaluate failure probability. Statistical information of material strength has not been provided enough yet. In this report, the statistical properties of material strength was estimated for SUS304, 316FR steel and some other austenitic stainless steels. These materials are registered in the JSME code of design and construction of fast reactors, so test data used for developing the code were used as much as possible in this report.
14MI51 Boreholes)Kuroiwa, Hiroshi*; Kawamoto, Koji; Yamada, Nobuto; Sasao, Eiji
JAEA-Data/Code 2015-003, 108 Pages, 2015/06
JAEA-Data-Code-2015-003.pdf:10.4MBJAEA-Data-Code-2015-003(errata).pdf:1.51MB
JAEA-Data-Code-2015-003-appendix(CD-ROM).zip:1150.87MB
Japan Atomic Energy Agency (JAEA) is performing the Mizunami Underground Research Laboratory (MIU) Project, which is a scientific study of the deep geological environment as a basis of research and development for geological disposal of high level radioactive wastes (HLW), in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in the crystalline rock. The MIU Project has three overlapping phases, Surface-based investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III). This report compiles the data of results from borehole investigations which has been carried out in the research gallery in the fiscal year from 2012 to 2014. These data include results of core observation, geophysical logging, and so on.
Ishibashi, Masayuki; Sasao, Eiji
JAEA-Data/Code 2015-004, 8 Pages, 2015/06
JAEA-Data-Code-2015-004.pdf:2.0MBJAEA-Data-Code-2015-004-appendix(CD-ROM).zip:3.61MB
Japan Atomic Energy Agency (JAEA) at 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 fracture in the Toki Granite, central Japan, obtained by deep borehole investigation, drilled from the ground surface.
Kurosawa, Ryohei; Okada, Shota; Sakai, Akihiro; Nakata, Hisakazu; Amazawa, Hiroya
JAEA-Data/Code 2015-005, 82 Pages, 2015/06
JAEA-Data-Code-2015-005.pdf:3.47MB
The calculation tool of neutron flux at materials within and around the research reactor was developed so that the user more easily evaluate radioactivity inventory in radioactive waste generated from the decommissioning of research reactors at various conditions. The tool consists of some computer programs which calculate macroscopic effective cross section at materials, calculate the neutron flux at materials within and around the research reactor, and edit the neutron flux to evaluate the radioactive inventory. This report describes the outline of evaluation method of neutron flux at materials within and around the research reactor, the structure and functions of the calculation tool of neutron flux, input and output data, and sample run with the tool.
Ueno, Tetsuro; Takeuchi, Ryuji
JAEA-Data/Code 2015-006, 22 Pages, 2015/06
JAEA-Data-Code-2015-006.pdf:5.05MBJAEA-Data-Code-2015-006-appendix(CD-ROM).zip:14.52MB
Tono Geoscience Center of Japan Atomic Energy Agency (JAEA) has carried out the subsurface water balance observation in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for calibration of hydrogeological model. In the subsurface water balance observations, precipitation data and river flow rate have been observed in the Garaishi River and the Hiyoshi River watersheds. The missing or abnormal data in the monitoring data during the fiscal year 2013 were complemented or corrected, and these data were compiled in data set.
Ueno, Tetsuro; Takeuchi, Ryuji
JAEA-Data/Code 2015-007, 55 Pages, 2015/06
JAEA-Data-Code-2015-007.pdf:9.53MBJAEA-Data-Code-2015-007-appendix(CD-ROM).zip:194.09MB
Tono Geoscience Center of Japan Atomic Energy Agency (JAEA) has carried out the subsurface water balance observation in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for calibration of hydrogeological model. In the subsurface water balance observations, meteorological data, river flow rate, groundwater level and soil moisture have been observed in the Shoma River watershed, the Shoma River model watershed and the MIU Construction Site. After missing or abnormal data in the monitoring data from the fiscal year 2013 were complemented or corrected, the data were compiled in data set. Furthermore the groundwater recharge rates in the Hazama River watershed were calculated using the river flow rate data obtained from the environment survey in the MIU construction work in the fiscal year 2013.
Nomoto, Yasunobu; Aihara, Jun; Nakagawa, Shigeaki; Isaka, Kazuyoshi; Ohashi, Hirofumi
JAEA-Data/Code 2015-008, 39 Pages, 2015/06
JAEA-Data-Code-2015-008.pdf:10.32MB
HTFP is a calculation code for amount of additionally released fission product (FP) from fuel rods of pin-in-type according to transient of core temperature at the accident of high temperature gas-cooled reactors (HTGRs). This code analyzes FP release inventory from core according to the transient of core temperature at the accident as an input data and considering FP release rate from a fuel compact and a graphite sleeve and radioactive decay of FP. This report describes the outline of HTFP code and its input data. The computed solutions using the HTFP code were compared to those of HTCORE code, which was used for the design of the High Temperature Engineering Test Reactor (HTTR) to validate the analysis models of the HTFP code. The comparison of HTFP code results with HTCORE code results showed the good agreement.
Yokoyama, Kenji; Jin, Tomoyuki; Hirai, Yasushi*; Hazama, Taira
JAEA-Data/Code 2015-009, 120 Pages, 2015/07
JAEA-Data-Code-2015-009.pdf:1.93MB
The second version of the versatile reactor analysis code system, MARBLE2, has been developed. A lot of new functions have been added inMARBLE2 by using the base technology developed in the first version (MARBLE1). Introducing the remaining functions of the conventional code system (JOINT-FR and SAGEP-FR), MARBLE2 enables one to execute almost all analysis functions of the conventional code system with the unified user interfaces of its subsystem, SCHEME. In particular, the sensitivity analysis functionality is available in MARBLE2. On the other hand, new built-in solvers have been developed, and existing ones have been upgraded. Furthermore, some other analysis codes and libraries developed in JAEA have been consolidated and prepared in SCHEME. In addition, several analysis codes developed in the other institutes have been additionally introduced as plug-in solvers. Consequently, 
-ray transport calculation and heating evaluation become available. As for another subsystem, ORPHEUS, various functionality updates and speed-up techniques have been applied based on user experience of MARBLE1 to enhance its usability.
Aoyagi, Kazuhei; Sakurai, Akitaka; Niunoya, Sumio*
JAEA-Data/Code 2015-010, 190 Pages, 2015/10
JAEA-Data-Code-2015-010.pdf:18.7MBJAEA-Data-Code-2015-010-appendix(CD-ROM).zip:127.68MB
The objective of this report is to investigate the three dimensional stress state in the 350m pumping station at the Horonobe Underground Research Laboratory. For the measurement, four boreholes were drilled; three 20.0m long boreholes and one 6.0m long borehole. 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 12 MPa, two times larger than overburden pressure. Furthermore, the ratio between maximum to minimum principal stress was 6. On the other hand, without considering the stress condition causing breakout, the maximum principal stress was 6 MPa; almost same as overburden pressure; the ratio between maximum to minimum principal stress was 2.7, thus the result was almost coincide with the result of surface-based investigation. The orientation of the maximum principal stress was N30W, dipping 45
from vertical axis.
Aoyagi, Kazuhei; Sakurai, Akitaka; Niunoya, Sumio*
JAEA-Data/Code 2015-011, 182 Pages, 2015/09
JAEA-Data-Code-2015-011.pdf:33.41MBJAEA-Data-Code-2015-011-appendix(CD-ROM).zip:41.95MB
The objective of this report is to investigate the three dimensional stress state in the 250 m Niche off the South Shaft No.1 at the Horonobe Underground Research Laboratory. For the measurement, three 20.0m long boreholes 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 of the in situ stress state measurement around the experimental area, the orientation of the maximum principal stress is estimated to be between E-W and ENE-WSW, dipping almost horizontal direction. This result agrees well with the estimated orientation of the main principal stress, the location of the borehole wall breakouts in 10-E250-M01 and the orientation of the generated crack in 10-E250-M03. The value of the maximum principal stress was 3.97 MPa.
Aoyagi, Kazuhei; Sakurai, Akitaka; Niunoya, Sumio*
JAEA-Data/Code 2015-012, 171 Pages, 2015/09
JAEA-Data-Code-2015-012.zip:33.31MBJAEA-Data-Code-2015-012.pdf:28.27MB
The objective of this report is to investigate the three dimensional stress state in the 250 m Niche off the West Shaft No.1 at the Horonobe Underground Research Laboratory. For the measurement, three 20.0m long boreholes 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 of the in situ stress state measurement around the experimental area, the orientation of the maximum principal stress was estimated to be ESE-WNW, dipping 70 from the vertical axis. The orientation of the minimum principal stress was NEN-SWS, dipping 60 from vertical axis. The orientation of the principal stresses is almost coincided with the direction of borehole breakouts and longitudinal crack induced in the boreholes. The values of the maximum and minimum principal stresses were 2.6 MPa and 2.1 MPa, respectively.
Nakayama, Masashi; Ono, Hirokazu; Nakayama, Mariko*; Kobayashi, Masato*
JAEA-Data/Code 2015-013, 53 Pages, 2015/09
JAEA-Data-Code-2015-013.pdf:9.78MBJAEA-Data-Code-2015-013(errata).pdf:0.37MBJAEA-Data-Code-2015-013-appendix(CD-ROM).zip:5.76MB
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 formation at Horonobe, northern Hokkaido. The URL 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", over a period of around 20 years. 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 G.L.-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. The period of data acquisition is from December, 2014 to March, 2015. It will be periodically published summarized data of EBS experiment.
Yoshino, Hiromitsu; Kishi, Atsuyasu*; Yokota, Hideharu
JAEA-Data/Code 2015-014, 42 Pages, 2015/09
JAEA-Data-Code-2015-014.pdf:11.38MBJAEA-Data-Code-2015-014-appendix(CD-ROM).zip:4.26MB
Long-term pore-pressure-monitoring has been performed using HDB-111 and PB-V01 boreholes in the Horonobe Underground Research Laboratory Project. This report summarizes the results obtained from the starting of monitoring to March 2015.
Okumura, Keisuke
JAEA-Data/Code 2015-015, 162 Pages, 2015/10
JAEA-Data-Code-2015-015.pdf:3.99MBJAEA-Data-Code-2015-015-appendix(CD-ROM).zip:3.38MB
MOSRA-SRAC is a lattice calculation module of the Modular code System for nuclear Reactor Analyses (MOSRA). This module performs the neutron transport calculation for various types of fuel elements including existing light water reactors, research reactors, etc. based on the collision probability method with a set of the 200-group cross-sections generated from the Japanese Evaluated Nuclear Data Library JENDL-4.0. It has also a function of the isotope generation and depletion calculation for up to 234 nuclides in each fuel material in the lattice. In these ways, MOSRA-SRAC prepares the burn-up dependent effective microscopic and macroscopic cross-section data to be used in core calculations.
Sugawara, Takanori; Kodama, Yasuhiro*; Nishihara, Kenji; Hirai, Yasushi*
JAEA-Data/Code 2015-016, 27 Pages, 2015/10
JAEA-Data-Code-2015-016.pdf:0.87MB
The general-purpose reactor analysis code system, MARBLE, has been used to calculate neutron transport and burn-up calculations for Accelerator-Driven System (ADS). In the burn-up calculation of MARBLE, fission product (FP) nuclides had been treated as lump FP in the past. It meant that MARBLE was unable to treat residual nuclides such as rare-earth ones which would be generated by the fuel exchange of the ADS. To treat residual nuclides, ORIGEN2, which was one of the most famous burn-up calculation codes was implemented to MARBLE. By the implementation of ORIGEN2 code, it was available to treat FP nuclides by each nuclide and to consider the residual nuclides in the ADS burn-up calculation.
Aoyagi, Kazuhei; Kawate, Satoshi
JAEA-Data/Code 2015-017, 118 Pages, 2015/12
JAEA-Data-Code-2015-017.pdf:17.67MBJAEA-Data-Code-2015-017-appendix-Disc1(DVD-ROM).zip:412.15MBJAEA-Data-Code-2015-017-appendix-Disc2(DVD-ROM).zip:233.57MBJAEA-Data-Code-2015-017-appendix-Disc3(DVD-ROM).zip:233.62MBJAEA-Data-Code-2015-017-appendix-Disc4(DVD-ROM).zip:209.35MBJAEA-Data-Code-2015-017-appendix-Disc5(DVD-ROM).zip:1700.64MB
In the Horonobe Underground Research Laboratory (URL) Project, construction of the Ventilation Shaft, the East and West Access Shafts and the drifts has been conducted as a phase II research. In the research, observation of the lithofacies and fractures, and in-situ tests are conducted in each face. In addition, measuring instruments such as tunnel lining concrete stress meter and extensometer are installed in particular face for the purpose of the validation of the results of predictive analysis, conducted in phase I. This report summarizes the measurements data acquired at the 350 m Gallery and the ventilation shaft.
Takai, Shizuka; Takayama, Hideki*; Takeda, Seiji
JAEA-Data/Code 2015-018, 96 Pages, 2015/11
JAEA-Data-Code-2015-018.pdf:4.24MB
In the safety assessment for the high-level radioactive waste geological disposal, scenarios need to be developed in consideration of influence on barrier features by accidents and human factors caused by application of engineering technologies at each stage of site characterization, construction, operation and closure of disposal facility. To develop scenarios on application of engineering technologies from the point of view of safety regulation, deviation events which are deviated states of engineered and natural barriers from intended states were specified and possible evolution of features of barriers or loss/reduction of safety functions of barriers was shown as a scenario in JAEA-Data/Code 2014-026. In this study, we compiled information of existence of engineering measures against the accidents and human factors and deviation events, application performance and development status of the measures. From this information, we identified deviation events which need developing of engineering measures as remarkable deviation events. These results were integrated as a database that could support development of scenarios caused by application of engineering technologies to geological disposal.
Ishigami, Tsutomu; Shimada, Taro; Seki, Masaya; Mukai, Masayuki
JAEA-Data/Code 2015-019, 122 Pages, 2015/12
JAEA-Data-Code-2015-019.pdf:3.65MB
In ensuring compliance with the criterion of site release as the final stage of termination of decommissioning of nuclear facilities, it is supposed to confirm the radioactivity concentration obtained by measurement in the site is less than or equal to the concentration corresponding to the criterion. It is needed to estimate the distribution and mean of radioactivity concentration in the evaluation unit using a number of measured data. It is further needed to compare the estimated result with the concentration corresponding to the criterion of site release and to decide if the evaluation unit should comply with the criterion. The estimated result exhibits uncertainty depending on the number of measurement points, which results in a certain probability of the occurrence of decision error according to the uncertainty. It is important to decide the number of measurement points required by revealing a relationship of the error probability to the number of measurement points for site security. We have developed the ESRAD2 (Estimation of Spatial RadioActivity Distribution program version 2), which is an extended version of the existing ESRAD, for estimating the mean of radioactivity concentration and calculating the number of measurement points required according to the error probability. This report describes a method for ensuring compliance with the criterion of site release, structure and functions, input file format, output examples, execution method of ESRAD2, and sample run with ESRAD2.
Asami, Makoto; Watahiki, Hiromi; Oi, Takao; Shibata, Atsuhiro; Ashida, Takashi
JAEA-Data/Code 2015-020, 80 Pages, 2015/11
JAEA-Data-Code-2015-020.pdf:45.07MBJAEA-Data-Code-2015-020-appendix(DVD-ROM).zip:602.44MB
FY2014 edition of the analysis results on contaminated water in the circulating system and on rubbles/soils of Fukushima Daiichi Nuclear Power Station (1F NPS) was compiled. This technical report shows the function of the electronic file of the FY2014 edition of the analysis results on contaminated water and on rubbles/soils and presents the user manual with example and gives the electronic file by appendix CD.
Ono, Hirokazu; Takeda, Masaki; Matsuoka, Toshiyuki
JAEA-Data/Code 2015-021, 52 Pages, 2016/01
JAEA-Data-Code-2015-021.pdf:18.94MBJAEA-Data-Code-2015-021-1-1appendix(CD-ROM).zip:14.52MBJAEA-Data-Code-2015-021-1-2-1appendix(CD-ROM).zip:217.31MBJAEA-Data-Code-2015-021-1-2-2appendix(CD-ROM).zip:296.07MBJAEA-Data-Code-2015-021-1-2-3appendix(CD-ROM).zip:191.06MBJAEA-Data-Code-2015-021-1-3appendix(CD-ROM).zip:74.64MBJAEA-Data-Code-2015-021-1-4appendix(CD-ROM).zip:195.28MBJAEA-Data-Code-2015-021-2appendix(CD-ROM).zip:0.12MB
HDB-1 to HDB-11 were drilled at Hokushin Area of Horonobe Town, Teshio District, Hokkaido, Japan in order to investigate the characteristic of deep underground. This report summarize the results of the work carried out with the purpose of clarifying the geological, mechanical characteristics from the surface to the deeper part of this borehole.
Takeda, Takeshi
JAEA-Data/Code 2015-022, 58 Pages, 2016/01
JAEA-Data-Code-2015-022.pdf:3.31MB
The SB-HL-12 test simulated PWR 1% hot leg SBLOCA under assumptions of total failure of HPI system and non-condensable gas (nitrogen gas) inflow. SG depressurization by fully opening relief valves in both SGs as AM action was initiated immediately after maximum fuel rod surface temperature reached 600 K. After AM action due to first core uncovery by core boil-off, the primary pressure decreased, causing core mixture level swell. The fuel rod surface temperature then increased up to 635 K. Second core uncovery by core boil-off took place before LSC induced by steam condensation on ACC coolant injected into cold legs. The core liquid level recovered rapidly after LSC. The fuel rod surface temperature then increased up to 696 K. The pressure difference became larger between the primary and SG secondary sides after nitrogen gas inflow. Third core uncovery by core boil-off occurred during reflux condensation. The maximum fuel rod surface temperature exceeded 908 K.
Sakurai, Akitaka; Aoyagi, Kazuhei; Fujita, Tomoo; Motoshima, Takayuki*
JAEA-Data/Code 2015-023, 46 Pages, 2016/02
JAEA-Data-Code-2015-023.pdf:48.03MBJAEA-Data-Code-2015-023-appendix(CD-ROM).zip:48.51MB
In a high level radioactive waste (HLW) disposal project, it is necessary to investigate the long-term behavior of thermos-hydro-mechanical-chemical of the rock mass around the engineered barrier system of the HLW waste for the safety assessment of the disposal system. In addition, long-term stability of the rock mass around the galleries are required for the disposal facility. Considering these backgrounds, the authors measure the deformation behavior of the vertical pit drilled on the floor of the 350 m gallery in the Horonobe Underground Research Laboratory. In situ measurements of the deformation of the pit and rock mass around the pit was conducted to apply to the assessment of the long-term deformation behavior. The authors describe the drilling of the vertical pit, geological observation, specification of the measurement instrument, measurement method, and result of the measurement in this report.
Kusano, Tomohiro; Ishii, Eiichi
JAEA-Data/Code 2015-024, 6 Pages, 2016/02
JAEA-Data-Code-2015-024.zip:2.23MBJAEA-Data-Code-2015-024.pdf:7.54MB
Japan Atomic Energy Agency (JAEA) is performing the Horonobe Underground Research Laboratory Project, which includes a scientific study of the deep geological environment as a basis of research and development for geological disposal of high level radioactive wastes (HLW), in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in the sedimentary rock. This report aims at compiling fracture data of drill core obtained from the Horonobe Underground Research Laboratory Project (Phase 1).
Haraga, Tomoko; Tobita, Minoru*; Takahashi, Shigemi*; Ishimori, Kenichiro; Kameo, Yutaka
JAEA-Data/Code 2015-025, 52 Pages, 2016/03
JAEA-Data-Code-2015-025.pdf:1.92MB
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 verify that the cleared dismantled materials conform to the clearance levels. A simple and rapid radioactivity determination method for radioactive waste samples was developed in Department of Decommissioning and Waste Management. For the demonstration, the simple and rapid radioactivity determination method was applied to metal samples, which were taken from dismantled pipes of Fugen. This report summarizes the radioactivity data obtained from the analysis of those samples.
Nakayama, Hiromasa; Nagai, Haruyasu
JAEA-Data/Code 2015-026, 37 Pages, 2016/03
JAEA-Data-Code-2015-026.pdf:2.48MB
We developed LOcal-scale High-resolution atmospheric DIspersion Model using Large-Eddy Simulation (LOHDIM-LES). This dispersion model is designed based on LES which is effective to reproduce unsteady behaviors of turbulent flows and plume dispersion. The basic equations are the continuity equation, the Navier-Stokes equation, and the scalar conservation equation. Buildings and local terrain variability are resolved by high-resolution grids with of a few meters and these turbulent effects are represented by immersed boundary method. In simulating atmospheric turbulence, boundary layer flows are generated by a recycling turbulent inflow technique in a driver region set up at the upstream of the main analysis region. This turbulent inflow data are imposed at the inlet of the main analysis region. By this approach, the LOHDIM-LES can provide detailed information on wind velocities and plume concentration in the investigated area.
Tachi, Yukio; Suyama, Tadahiro
JAEA-Data/Code 2015-027, 40 Pages, 2016/03
JAEA-Data-Code-2015-027.pdf:3.4MB
Sorption and diffusion of radionuclides in buffer materials (bentonite) and rocks are the key processes in the safe geological disposal of radioactive waste, because migration of radionuclides in these barrier materials is expected to be diffusion-controlled and retarded by sorption processes. Japan Atomic Energy Agency (JAEA) has developed databases of sorption and diffusion parameters in bentonites and rocks. The present report focuses on updating of the diffusion database (JAEA-DDB) as basis of PA-related parameter setting. This includes an overview of database structure, contents and functions including additional data evaluation function. The diffusion data are updated by focusing on bentonites, granites and mudstones related to our recent PA activities. As a result, about 3,500 data from 221 references were added, total number of diffusion data in the JAEA-DDB reached about 5,000. The updated JAEA-DDB is expected to make it possible to obtain quick overview of the available data, and to have suitable access to the respective data for PA-related diffusion parameter setting in effective, traceable and transparent manner.
Tachi, Yukio; Suyama, Tadahiro
JAEA-Data/Code 2015-028, 60 Pages, 2016/03
JAEA-Data-Code-2015-028.pdf:1.96MB
Sorption and diffusion of radionuclides in buffer materials and rocks are the key processes in the safe geological disposal of radioactive waste, because migration of radionuclides in this barrier is expected to be diffusion-controlled and retarded by sorption processes. For this purpose, Japan Atomic Energy Agency has developed databases of sorption and diffusion parameters in buffer materials and rocks. The present report focuses on developing and updating of the sorption database as basis of integrated approach for PA-related Kd setting and mechanistic sorption model development. This includes an overview of database structure, contents and functions including additional data evaluation function focusing on multi-parameter dependence, operating method, PA-related applications of the web-based JAEA-SDB. Kd data and their QA results are updated by focusing our recent activities on the Kd setting and mechanistic model development. As a result, 11,206 Kd data from 81 references are added, total Kd values in the JAEA-SDB are about 58,000. The QA/classified Kd data are about 39% for all Kd data in JAEA-SDB. The updated JAEA-SDB is expected to make it possible to obtain quick overview of the available data, and to have suitable access to the respective data for PA-related Kd setting in effective, traceable and transparent manner.
Okamoto, Tsutomu; Minato, Futoshi; Koura, Hiroyuki; Iwamoto, Osamu
JAEA-Data/Code 2015-029, 30 Pages, 2016/03
JAEA-Data-Code-2015-029.pdf:1.81MB
The booklet "chart of the nuclides" is issued every 4 years since 1976 from Nuclear Data Center, JAEA. The chart of the nuclides for WWW (World Wide Web) was developed in 1999 in order to be available from internet browser. Internet connection speeds, browser functions and JavaScript libraries has, however, progressed at present compared with the internet technology in those days. In connection with the release of the 2014 edition of the chart of the nuclides, the interface of the WWW chart of the nuclides has been improved by introducing new internet technologies aiming at enhancing convenience on accessibilities via browsers. We introduced a scrolling screen that would make capabilities of easy screen movement on a map with the addition of the drag scrolling function. Considering smart phone access, the light-weight edition which introduced automatic switch was prepared. The new system results in reduction in access time and usefulness in mobile environment. The method of making figures of the chart was reconsidered due to addition of new decay schemes to the 2014 edition. SVG (Scalable Vector Graphics) was adopted so as to make figures easily. It is concluded that the accessibilities of WWW chart of the nuclides are substantially improved from the previous version by introducing the new technologies.
Katakura, Junichi*; Minato, Futoshi
JAEA-Data/Code 2015-030, 97 Pages, 2016/03
JAEA-Data-Code-2015-030.pdf:1.01MB
JENDL Decay Data File 2015 (JENDL/DDF-2015) has been produced. The decay data of nuclides with mass numbers from 1 to 260 are included. The nuclides with unknown - and/or beta-emission are also included in order to keep decay chains. The data of 1,284 fission product nuclides with mass from 66 to 172 remain unchanged from JENDL/FPD-2011 except several corrections which had been claimed by users, and those of the newly added 1,953 nuclides are taken from ENSDF. Finally, the decay data of 3,237 nuclides including 244 stable nuclides were compiled as JENDL/DDF-2015 file.
Ueno, Tetsuro; Takeuchi, Ryuji
JAEA-Data/Code 2015-031, 61 Pages, 2016/03
JAEA-Data-Code-2015-031.pdf:9.15MBJAEA-Data-Code-2015-031-1appendix(DVD-ROM).zip:174.29MBJAEA-Data-Code-2015-031-2-1appendix(DVD-ROM).zip:86.67MBJAEA-Data-Code-2015-031-2-2appendix(DVD-ROM).zip:268.33MBJAEA-Data-Code-2015-031-2-3appendix(DVD-ROM).zip:569.4MBJAEA-Data-Code-2015-031-2-4appendix(DVD-ROM).zip:103.25MBJAEA-Data-Code-2015-031-2-5appendix(DVD-ROM).zip:0.4MB
Tono Geoscience Center of Japan Atomic Energy Agency (JAEA) has carried out the subsurface water balance observation in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for calibration of hydrogeological model. In the subsurface water balance observations, meteorogical data, river flow rate, groundwater level and soil moisture have been observed in the Shoma River watershed, the Shoma River model watershed and the MIU Construction Site. After missing or abnormal data in the monitoring data from the fiscal year 2014 were complemented or corrected, the data were compiled in data set. Furthermore the groundwater recharge rates in the Hazama River watershed were calculated using the river flow rate data obtained from the environment survey in the MIU construction work in the fiscal year 2014. Because many data were accumulated, these observations were finished in the end of March, 2015.
Ueno, Tetsuro; Takeuchi, Ryuji
JAEA-Data/Code 2015-032, 30 Pages, 2016/03
JAEA-Data-Code-2015-032.pdf:9.65MBJAEA-Data-Code-2015-032-appendix(CD-ROM).zip:593.7MB
Tono Geoscience Center of Japan Atomic Energy Agency (JAEA) has carried out the subsurface water balance observation in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for calibration of hydrogeological model. In the subsurface water balance observations, precipitation data and river flowrate have been observed in the Garaishi River and Hiyoshi River watersheds. The missing or abnormal data in the monitoring data during the fiscal year 2014 were complemented or corrected, and these data were compiled in data set. Because many data were accumulated, these observations were finished in the end of March, 2015.
Kasugai, Yoshimi; Harada, Masahide; Kai, Tetsuya; Oi, Motoki; Meigo, Shinichiro; Maekawa, Fujio
JAEA-Data/Code 2015-033, 28 Pages, 2016/03
JAEA-Data-Code-2015-033.pdf:1.78MB
The high-energy neutron fluxes and spectra around the mercury spallation neutron source at MLF of J-PARC were measured by the multi-foil activation method. The threshold energies of neutron reactions utilized in this experiment covered from 0.1 to 50 MeV. The foil irradiation was carried out on the first beam-run of MLF from May 30th to 31th, 2008. After the irradiation, the induced radioactivity of each foil was measured using an HPGe detector, and the neutron-induced reaction-rate distribution around the mercury target was determined. Using these data, the high-energy neutron fluxes and spectra were deduced with unfolding method in which the neutron spectra calculated with PHITS code were used as the initial-guess spectra. By comparison between the initial and the unfolded spectra, it was shown that most of the calculation results, which had been the basis of the neutronics design of the MLF target assembly, were consistent with the experimental data within 
30%.