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JAEA Reports

GSALab computer code for global sensitivity analysis

Liu, Q.; Homma, Toshimitsu; Nishimaki, Yuichiro*; Hayashi, Hiroko*; Terakado, Masato*; Tamura, Satoshi*

JAEA-Data/Code 2010-001, 57 Pages, 2010/03

JAEA-Data-Code-2010-001.pdf:16.81MB

For a risk assessment model of an engineering system, the uncertainties in the model inputs propagate through the model and lead to the uncertainty in the model output. In order to evaluate the model output uncertainty and the contribution of each model input to the output uncertainty, the computer code GSALab, which is based on Monte Carlo simulations, has been developed. It is composed of three parts, namely, random samples generation, uncertainty analysis and sensitivity analysis. In the part of sensitivity analysis, several global sensitivity indicators, including the popularly used variance-based indicators, are implemented. In addition, the GUI (Graphical User Interface) of GSALab has been developed for the user's convenience. In addition to risk assessment models, it is also possible to use GSALab for uncertainty and sensitivity analysis of a wide class of mathematical models.

JAEA Reports

Horonobe Underground Research Laboratory Project; The Results of the pilot borehole investigation of the ventilation shaft (PB-V01); Geophysical loggings

Funaki, Hironori; Asamori, Koichi; Sanada, Hiroyuki; Hatsuyama, Yoshihiro*; Yamamoto, Takuya*; Ijiri, Yuji*; Matsuoka, Kiyoyuki*; Kimura, Kazuhiro*; Lin, S.*; Kumagai, Toshifumi*

JAEA-Data/Code 2010-002, 151 Pages, 2010/06

JAEA-Data-Code-2010-002.pdf:43.13MB

JAEA is implementing Horonobe URL Project as research and development of geological disposal. The investigation of the pilot boring was carried out around the Ventilation shaft in order to decide grouting plan and plant of effluent treating. This report summarize as data-code results of geophysical loggings.

JAEA Reports

Log of refining and conversion facility dismantling; Progress in 2008FY

Editorial Committee of Refining and Conversion Facility Decommissioning Results

JAEA-Data/Code 2010-003, 308 Pages, 2010/05

JAEA-Data-Code-2010-003-01.pdf:40.71MB
JAEA-Data-Code-2010-003-02.pdf:62.39MB
JAEA-Data-Code-2010-003-03.pdf:10.06MB

The schedule which will finish dismantling of all equipment in a radiation controlled area is by the 2011 fiscal year. This report is a record of the dismantlement situation of the Refining and Conversion Facility in 2008 fiscal years. Concretely, dismantlement logs, dismantlement material, and secondary waste are published.

JAEA Reports

DOSE-Analyzer; A Computer program with graphical user interface to analyze absorbed dose inside a body of mouse and human upon external neutron exposure

Satoh, Daiki; Takahashi, Fumiaki; Shigemori, Yuji*; Sakamoto, Kensaku

JAEA-Data/Code 2010-004, 28 Pages, 2010/06

JAEA-Data-Code-2010-004.pdf:1.58MB

DOSE-Analyzer is a computer program to retrieve the dose information from a database and generate a graph through a user-friendly graphical interface. The database is constructed for absorbed dose, fluence, and energy distribution inside a body of mouse and human exposed upon external neutrons, which is calculated by our developed Monte-Carlo simulation method using voxel-type phantom and particle transport code PHITS. The input configuration such as irradiation geometry, subject, and energy is set by GUI. The results are tabulated at particle types, i.e. electron, proton, deuteron, triton, and alpha particle, and target organs on a data sheet of Microsoft Office Excel. Simple analysis to compare the output values for two subjects is also performed on DOSE-Analyzer. This report is a user manual of DOSE-Analyzer.

JAEA Reports

Development of grout materials for a geological disposal system for high-level radioactive waste

Fukuoka, Naomi; Shinkai, Fumiaki; Miura, Norihiko*; Nobuto, Jun*; Yamada, Tsutomu*; Naito, Morimasa

JAEA-Data/Code 2010-005, 353 Pages, 2010/07

JAEA-Data-Code-2010-005-01.pdf:8.91MB
JAEA-Data-Code-2010-005-02.pdf:46.47MB

High-level radioactive waste management in Japan is based on the multi-barrier concept, composed of the engineered barrier system and the surrounding geological formations. Although cementitious materials are commonly used for rock support, lining, and grouting, their pH plume are considered to have an adverse effect on long-term safety of a geological disposal system. In addition, during the emplacement of waste package with buffer material, it is required to limit amount of groundwater inflow into a disposal pit or tunnel to a certain level by grouting because the bentonite clay buffer is easy to swell in time by contact with the groundwater. Therefore, it is necessary to develop new grout materials with penetrability for smaller fractures. This report shows the most appropriate composition of new grout materials to be suitable for the in-situ experiment based on the result of indoor test.

JAEA Reports

Development of computation model on the GoldSim platform for the radionuclide transport in the geosphere with the time-dependent parameters

Koo, Shigeru*; Inagaki, Manabu

JAEA-Data/Code 2010-006, 41 Pages, 2010/06

JAEA-Data-Code-2010-006.pdf:1.39MB

In the HLW disposal system, numerical evaluation for radionuclide transport with the time-dependent parameters is necessary to evaluate various scenarios. In H12 report, numerical code MESHNOTE and TIGER were used for the evaluation of some natural phenomena scenarios that had to handle the time-dependent parameters. In the future, the necessity of handling the time-dependent parameters will be expected to increase, and more efficient calculation and improvement of quality control of input/output parameters will be required. Therefore, for the purpose of corresponding this requirement, a radionuclide transport model has been developed on the Goldsmith GoldSim is a general simulation software, that was used for the computation modeling of Yucca Mountain Project. The conceptual model, the mathematical model and the verification of the GoldSim Model are described in this report. In the future, application resources on this report will be able to upgrade for perturbation scenarios analysis model.

JAEA Reports

Monitoring of pore water pressure and groundwater chemistry at MSB-2 and MSB-4 boreholes; April, 2007 - March, 2008

Sai, Masataka; Hagiwara, Hiroki; Takeguchi, Naoto*; Yasue, Motoi*; Horita, Masakuni*; Mizuno, Takashi

JAEA-Data/Code 2010-007, 191 Pages, 2010/06

JAEA-Data-Code-2010-007.pdf:2.79MB

Japan Atomic Energy Agency (JAEA) has been carried out investigation to understand the variation of groundwater chemistry related to the construction of Mizunami Underground Research Laboratory (MIU) at Mizunami City, Gifu prefecture, Japan. This report compiles the summarized data set of pore water pressure and groundwater chemistry at MSB-2 and MSB-4 boreholes in the MIU construction site since April, 2007 to March, 2008.

JAEA Reports

Monitoring of pore water pressure and groundwater chemistry at MSB-2 and MSB-4 boreholes; April, 2008 - March, 2009

Sai, Masataka; Hagiwara, Hiroki; Ishihara, Eiji*; Horita, Masakuni*; Mizuno, Takashi

JAEA-Data/Code 2010-008, 158 Pages, 2010/06

JAEA-Data-Code-2010-008.pdf:2.47MB

Japan Atomic Energy Agency (JAEA) has been carried out investigation to understand the variation of groundwater chemistry related to the construction of Mizunami Underground Research Laboratory (MIU) at Mizunami City, Gifu prefecture, Japan. This report compiles the summarized data set of pore water pressure and groundwater chemistry at MSB-2 and MSB-4 boreholes in the MIU construction site since April, 2008 to March, 2009.

JAEA Reports

Development of adult Japanese voxel phantoms and their application to evaluation of radiation exposure doses

Sato, Kaoru; Takahashi, Fumiaki; Satoh, Daiki; Endo, Akira

JAEA-Data/Code 2010-009, 189 Pages, 2010/08

JAEA-Data-Code-2010-009.pdf:2.52MB

JAEA has developed two male and a female voxel phantoms using CT images of adult Japanese to study the effects of postures and body sizes on dose assessment. The three voxel phantoms consist of about 1 mm$$^{3}$$ size voxels, and the shapes and masses of organs are more realistically reproduced. The two male voxel phantoms were constructed from the CT images of an identical person taken in supine and in upright. Therefore, it is possible to clarify the impact of posture on dose assessment by comparing directly organ doses of two phantoms. The present report describes (1) the construction and characteristics of the JAEA voxel phantoms, (2) the effects of postures on the organ doses by photon emitters, and (3) the effects of body sizes on organ doses by external photon exposures. The present study provides valuable information to understand the effects of posture and body size on dose assessment in adapting dose conversion coefficients calculated using the reference voxel phantoms by ICRP.

JAEA Reports

Hydrochemical investigation at the Mizunami Underground Research Laboratory; Compilation of groundwater chemistry in the Mizunami group and Toki granite area (April, 2004 - March, 2008)

Sai, Masataka; Hagiwara, Hiroki; Matsushima, Hiroyuki*; Noda, Masatoshi*; Noda, Masaru*; Ando, Kenichi*; Tanaka, Tatsuya*; Ueda, Tadashi*; Honda, Yuko*; Mizuno, Takashi

JAEA-Data/Code 2010-010, 75 Pages, 2010/09

JAEA-Data-Code-2010-010.pdf:2.5MB

This report compiles data set of the groundwater chemistry obtained at Mizunami Underground Research Laboratory (MIU) between the fiscal year 2004 and the fiscal year 2007. These data includes groundwater chemistry of inflow in the shafts and sampled groundwater in the boreholes, which drilled from sub-stages of MIU and from surface (MSB-2, MSB-4, and MIZ-1). Basic information (e.g. sampling location, sampling date, sampling method, analytical method) are also described in terms of quality control and traceability.

JAEA Reports

Preparation of text files of JAEA-TDB for geochemical calculation programs

Kitamura, Akira; Yoshida, Yasushi*

JAEA-Data/Code 2010-011, 37 Pages, 2010/09

JAEA-Data-Code-2010-011.pdf:1.75MB

We established a thermodynamic database for performance assessment of geological disposal of high-level radioactive and TRU wastes. We prepared text files of the thermodynamic database (JAEA-TDB) for geochemical calculation programs of PHREEQC, EQ3/6 and Geochemist's Workbench. These text files are contained in the attached CD-ROM and will be available on our Website (http://migrationdb.jaea.go.jp/).

JAEA Reports

Data for estimating potential radiotoxicity of spent nuclear fuel

Nishihara, Kenji

JAEA-Data/Code 2010-012, 52 Pages, 2010/09

JAEA-Data-Code-2010-012.pdf:2.53MB

The potential radiotoxicity of spent nuclear fuel from nuclear power plants is defined as a summation of dose of individual nuclides in case of intake. In the present data base, the dominant nuclides for the potential radiotoxicity were selected from radioactive nuclides in the spent fuel, and dose coefficients to be used to convert radioactivity to dose were tabulated for the selected nuclides. Moreover, time evolution of the potential radiotoxicity was listed taking progenies into account for each actinide. The database enables simple estimation of time evolution of the potential radiotoxicity using an initial weight composition of the spent fuel. The potential radiotoxicity of a spent fuel from the light water reactor is shown as an example of the estimation. The database includes nuclides originated in the spent fuel and does not include those from decommissioning of the nuclear and allied plants.

JAEA Reports

Development of gamma cross section library for fast reactor gamma heating calculations

Chiba, Go; Hazama, Taira; Suzuki, Takayuki

JAEA-Data/Code 2010-013, 40 Pages, 2010/09

JAEA-Data-Code-2010-013.pdf:1.08MB

In order to evaluate gamma heating spatial distribution in fast reactors, a gamma cross section library UFGLIB.J40 and an utility to obtain macroscopic gamma constants for gamma-ray transport calculations are developed. The library UFGLIB.J40 is generated from the latest nuclear data library JENDL-4.0. The energy group structure for neutron is the JAERI fast set-type 70-group structure and that for photon is the MATXSLIB-type 42-group structure. The macroscopic gamma constant calculation utility generates gamma constants in binary format files from UFGLIB.J40 and the information given in PDS files yielded by a fast reactor lattice code SLAROM-UF. For verifications of UFGLIB.J40 and the utility, experimental data of gamma heating spatial distribution measured at the FCA XI-1 assembly are analyzed. Good agreement between calculation and experimental values is obtained.

JAEA Reports

Statistical compilation on meteorological observation in Horonobe from 1986 to 2009

Yamamoto, Yoichi; Maekawa, Keisuke

JAEA-Data/Code 2010-014, 105 Pages, 2010/10

JAEA-Data-Code-2010-014.pdf:3.21MB
JAEA-Data-Code-2010-014-appendix(CD-ROM).zip:31.65MB

Horonobe Underground Research Center has carried out meteorological observation in Horonobe-cho as a part of the Horonobe URL project. Meteorological observation in Horonobe-cho was started at Kaishin meteorological station on October 1986, and then Toikanbetsu meteorological station, Kamitoikan meteorological station, Horonobe downtown meteorological station, Hokushin meteorological station and Hokushin evapotranspiration tower were established sequentially, meteorological observations were conducted at a total of 6 points in the end. The meteorological observation data in Horonobe-cho from 1986 to 2009 is compiled in this report. Meteorological characteristics of Horonobe-cho are investigated using statistics data. Hourly data, daily data and monthly data are included in the data set, and the data set is recorded on CD-ROM.

JAEA Reports

Development of a framework for the neutronics analysis system for next generation, 4

Yokoyama, Kenji; Hirai, Yasushi*; Tatsumi, Masahiro*

JAEA-Data/Code 2010-015, 218 Pages, 2010/11

JAEA-Data-Code-2010-015.pdf:49.32MB

Japan Atomic Energy Agency promotes development of innovative analysis methods and models in fundamental studies for next-generation nuclear reactor systems. In order to efficiently and effectively reflect the latest analysis methods and models to primary design of prototype reactor and/or in-core fuel management for power reactors, a next-generation analysis system MARBLE has been developed. In the present study, functionalities for debugging have been enhanced by preparing an error handling mechanism in order to provide higher level of usability for users of the framework. Other functionalities have been also developed to deal with complex calculation routes with corrections such as analysis of critical experiments by introducing a mechanism for flexible handling of computational procedures.

JAEA Reports

Sophistication of burnup analysis system for fast reactor, 2

Yokoyama, Kenji; Hirai, Yasushi*; Tatsumi, Masahiro*

JAEA-Data/Code 2010-016, 92 Pages, 2010/10

JAEA-Data-Code-2010-016.pdf:12.22MB

Development of burnup analysis system for fast reactors with modularity and flexibility is being done that would contribute to actual core design work and improvement of prediction accuracy. In this fiscal year the present study, by extending the prototype system, features for handling of control rods and energy collapse of group constants have been designed and implemented. In addition, a mechanism for database management has been developed by extending the idea on restart files in order to help user easily access arbitrary data of the results.

JAEA Reports

Curves and tables of neutron cross sections in JENDL-4.0

Namekawa, Masakazu; Katakura, Junichi

JAEA-Data/Code 2010-017, 822 Pages, 2010/09

JAEA-Data-Code-2010-017(errata).pdf:1.0MB
JAEA-Data-Code-2010-017(errata2).pdf:2.24MB
JAEA-Data-Code-2010-017-Part1-01.pdf:23.46MB
JAEA-Data-Code-2010-017-Part1-02.pdf:25.79MB
JAEA-Data-Code-2010-017-Part2-01.pdf:36.26MB
JAEA-Data-Code-2010-017-Part2-02.pdf:30.64MB

Neutron cross sections of 406 nuclides in JENDL-4.0 are presented in figures and tables. In the tables, shown are cross sections at 0.0253 eV and 14 MeV, Maxwellian average cross sections (kT = 0.0253 eV), resonance integrals and fission spectrum average cross sections. In the figures, shown are three kinds of figures of cross section curves at 300 K.

JAEA Reports

Development of safety assessment method for human intrusion scenario in Japan, 1; Drilling scenario database for safety assessment of geological disposal (Contract research)

Nagasawa, Hirokazu; Takeda, Seiji; Kimura, Hideo; Sasaki, Toshihisa*

JAEA-Data/Code 2010-018, 85 Pages, 2010/11

JAEA-Data-Code-2010-018.pdf:1.94MB

In deep geological disposal or intermediate depth disposal, human intrusion, i.e. accidental excavation or drilling into the disposal site, may make a direct or indirect effect on the disposal system. Assessment of the human intrusion would need the examination of institutional control to reduce the probability of the intrusion occurring, the estimation of its probability, and the development of method to estimate its associated exposure of persons, as well as some foreign countries. Assuming that drilling action into the disposal site especially leads to the human proximity to the radioactive waste or the damage to the barrier system (drilling scenario), we have collected both the data on borehole drilling implemented in Japan and information on actual situation of drilling activities. We have developed an assembly of the information mentioned above as database, including the model parameters used in the code to assess radiation dose for drilling scenario.

JAEA Reports

Development of safety assessment method for human intrusion scenario in Japan, 2; Development of a human intrusion scenario evaluation code in radioactive waste disposal (Contract research)

Takeda, Seiji; Sasaki, Toshihisa*; Nagasawa, Hirokazu; Kimura, Hideo

JAEA-Data/Code 2010-019, 61 Pages, 2010/11

JAEA-Data-Code-2010-019.pdf:1.47MB

In deep geological disposal or intermediate depth disposal, human intrusion, i.e. accidental excavation or drilling into the disposal site, may make a direct or indirect effect on the disposal system. Assessment of the human intrusion would need the examination of institutional control to reduce the probability of the intrusion occurring, the estimation of its probability, and the development of method to estimate its associated exposure of persons, as well as some foreign countries. Assuming that drilling action into the disposal site especially leads to the human proximity to the radioactive waste or the damage to the barrier system (drilling scenario), we have developed the evaluation code of radiological effect from the human intrusion into radioactive waste disposal system (HUINT). The evaluation code of human intrusion scenario, HUINT, can calculate the radiation exposure dose for the workers of a series of actions accompanied with drilling and for the workers and public people concerned with the reuse of drilling cores, identified with the actual information on drilling action in Japan. This report provides the descriptions of mathematical models on the drilling scenario, input specification and user information for execution of HUINT (user manual), and the result of verification for calculation with the models in HUINT.

JAEA Reports

Calculation of dose coefficients and concentration limits based on tissue weighting factors, et al. revised in the ICRP 2007 Recommendations (Contract research)

Manabe, Kentaro; Endo, Akira

JAEA-Data/Code 2010-020, 148 Pages, 2010/11

JAEA-Data-Code-2010-020.pdf:1.57MB
JAEA-Data-Code-2010-020(errata).pdf:0.11MB

The dose coefficients and concentration limits provided by laws and their relevant public notices in Japan are based on the 1990 Recommendations of the International Commission on Radiological Protection (ICRP). In 2007, the ICRP published the new Recommendations which supersede the 1990 Recommendations. The 2007 Recommendations update tissue and radiation weighting factors to estimate equivalent and effective doses. Therefore, it is important to clarify the impact of these revisions on dose coefficients et al. in adopting the 2007 Recommendations for the system of radiation protection. In this study, dose coefficients et al. have been calculated using the revised tissue weighting factors and compared with those based on the 1990 Recommendations. For most nuclides, the dose coefficients calculated using weighting factors of the 2007 Recommendations decrease for inhalation and remain the same for ingestion. It was identified that the difference in dose coefficients is mainly due to the change in the procedure for calculating equivalent dose rather than the update of the weighting factors.

JAEA Reports

Analysis method of AC loss and temperature margin in forced flow cooled superconductors

Ichige, Toshikatsu; Murakami, Haruyuki; Kizu, Kaname; Yoshida, Kiyoshi

JAEA-Data/Code 2010-021, 45 Pages, 2010/12

JAEA-Data-Code-2010-021.pdf:6.52MB

The superconducting coil cannot operate after the quench that its conductor temperature becomes above the critical temperature and normal reason expands explosively. It is important to keep enough temperature margin from the operating temperature to the current sharing temperature. The forced flow conductor is adopted for the Tokamak machine because the mechanical strength and electrical high voltage are required. The performance of its conductor is depended on the magnetic field and temperature. This analysis method is validated by the comparison between experimental data and this analysis. This analysis method can evaluate the temperature margin of the superconducting conductor along its cooling length and during all operation scenarios, in case of the inlet temperature and the mass flow rate for the cooling condition. This analysis method can provide analysis results for selection of conductor parameters and for optimizing of the cooling condition from the cryoplant.

JAEA Reports

PHITS: Particle and Heavy Ion Transport code System, Version 2.23

Niita, Koji*; Matsuda, Norihiro; Iwamoto, Yosuke; Iwase, Hiroshi*; Sato, Tatsuhiko; Nakashima, Hiroshi; Sakamoto, Yukio; Sihver, L.*

JAEA-Data/Code 2010-022, 189 Pages, 2010/10

JAEA-Data-Code-2010-022.pdf:1.89MB

The Particle and Heavy-Ion Transport code System PHITS has been developed under the collaboration of JAEA, RIST and KEK, as an upgraded version of the NMTC/JAM code developed. PHITS can deal with the transport of all particles and heavy ions over wide energy ranges, using several nuclear reaction models and nuclear data libraries. The geometrical configuration of the simulation can be setup by GG (General Geometry) or CG (Combinatorial Geometry). Various quantities such as heat, track length and production yields can be deduced from the simulation, using implemented estimator functions called "tally". The code also has a function to draw 2D figures of the calculated results as well as the setup geometries, using ANGEL. Owing to these features, PHITS has been widely used for various purposes such as designs of accelerator shielding, radiation therapy and space exploration. This document provides the manual of PHITS.

JAEA Reports

Development of the Monju core safety analysis numerical models by Super-COPD code

Yamada, Fumiaki; Minami, Masaki*

JAEA-Data/Code 2010-023, 79 Pages, 2010/12

JAEA-Data-Code-2010-023.pdf:3.27MB

Japan Atomic Energy Agency constructed a computational model for safety analysis of Monju reactor core to be built into a modularized plant dynamics analysis code Super-COPD code, for the purpose of heat removal capability evaluation at the in total 21 defined transients in the annex to the construction permit application. The applicability of this model to core heat removal capability evaluation has been estimated by back to back result comparisons of the constituent models with conventionally applied codes and by application of the unified model.

JAEA Reports

Log of refining and conversion facility dismantling; Progress in 2009FY

Editorial Committee of Refining and Conversion Facility Decommissioning Results

JAEA-Data/Code 2010-024, 168 Pages, 2011/01

JAEA-Data-Code-2010-024.pdf:25.76MB

The schedule which will finish dismantling of all equipment in a radiation controlled area is by the 2011 fiscal year. This report is a record of the dismantlement situation of the Refining and Conversion Facility in 2009 fiscal years. Concretely, dismantlement logs, dismantlement material, and secondary waste are published.

JAEA Reports

Parallel processing for the simulation of electromagnetic terahertz wave emission

Higuchi, Kenji; Hiratsuka, Atsushi*; Endo, Tatsuro; Ota, Yukihiro; Machida, Masahiko

JAEA-Data/Code 2010-025, 84 Pages, 2011/02

JAEA-Data-Code-2010-025.pdf:1.94MB

We describe the parallelization and performance evaluation of the simulation program for emission of terahertz electromagnetic wave from high-Tc cuprate superconductors, where high performance was achieved as a result of tuning on multi-core system. Firstly the simulation space was divided for parallel processing, where MPI communication was implemented. The divided simulation space was further assigned to processes on multi-processors. Secondly parallel performance on each processor was accelerated by multi-threads implemented by OpenMP with a ratio at the number of core's. We have evaluated the parallelized program on HA8000 cluster system at Information Technology Center of the University of Tokyo, and, thus, achieved high performance in the analysis of terahertz electromagnetic wave emission from superconductors.

JAEA Reports

Evaluating and categorizing the reliability of distribution coefficient values in the sorption database, 4

Suyama, Tadahiro; Ganter, C.*; Kunze, S.*; Tachi, Yukio; Ochs, M.*

JAEA-Data/Code 2010-026, 72 Pages, 2011/02

JAEA-Data-Code-2010-026.pdf:1.05MB

Sorption of radionuclides in bentonites and rocks is one of the key processes in the safe geological disposal of radioactive waste. JAEA has developed sorption database (JAEA-SDB) which includes extensive compilation of sorption Kd data. JAEA has been continuing to update the SDB in view of potential future data needs, focusing on assuring the quality level and practical applications to Kd-setting for the geological environment. In this report, the QA/classification of selected entries in the JAEA-SDB, focusing on key radionuclides (Th, Np, Am, Se and Cs) sorption on tuff existing widely in geological environment, was done following the approach/guideline defined in our previous report. As a result, the reliability of 560 Kd values was evaluated and classified. This classification scheme is expected to make it possible to obtain quick overview of the available data from the SDB, and to have suitable access to the respective data for Kd-setting in PA.

JAEA Reports

Collection of URL measurement data in 2009 fiscal year at the Horonobe Underground Research Laboratory Project

Inagaki, Daisuke; Ishii, Eiichi; Niinuma, Hiroaki; Sanada, Hiroyuki; Tsusaka, Kimikazu; Sano, Michiaki*; Sawada, Sumiyuki

JAEA-Data/Code 2010-027, 151 Pages, 2011/02

JAEA-Data-Code-2010-027.pdf:9.75MB

In the Horonobe Underground Research Laboratory (URL) Project, construction of the ventilation shaft, the east shaft and the drifts has been conducted as a phase 2 research. In the research, observation of the lithofacies and fracture, and in-situ tests, simple elastic wave exploration, schmidt hammer test, equotip test, point load test are conducted in each face, and measuring instruments such as extensometer, rock-bolt axial force meter, shotcrete stress meter and tunnel lining concrete stress meter are installed in particular face. In addition, for the purpose of the validation of the results of predictive analysis, conducted in phase 1, about the amount of spring water during construction of underground facilities, data on the changes of amount of spring water and water quality is obtained. This report summarizes the measurements data acquired at the east shaft (GL-140 m - 210 m) and the 140 m drift.

JAEA Reports

Radioactivity analysis of metal samples taken from pipes of the Fugen

Kameo, Yutaka; Haraga, Tomoko; Ishimori, Kenichiro; Shimada, Asako; Tobita, Minoru*; Takahashi, Shigemi*; Takahashi, Kuniaki

JAEA-Data/Code 2010-028, 32 Pages, 2011/02

JAEA-Data-Code-2010-028.pdf:1.62MB

The Fugen Nuclear Power Station was shut down and decommissioning of the Fugen has been implemented. To calculate the scaling factor of radioactive waste or advance the clearance of dismantled materials, a large number of radioactivity concentration data of dismantled materials have to be accumulated. For these reasons, the simple and rapid radioactivity determination method was applied for metal samples, which were taken from pipes of the Fugen. The present report is summarized analytical procedures and obtained radioactivity data of the Fugen pipe samples.

JAEA Reports

Development of safety assessment model based on TRU-2 report using GoldSim

Ebina, Takanori*; Inagaki, Manabu*; Kato, Tomoko

JAEA-Data/Code 2010-029, 41 Pages, 2011/03

JAEA-Data-Code-2010-029.pdf:5.79MB

The safety assessment model at "Second Progress Report on Research and Development for TRU Waste Disposal in Japan" (TRU-2 report) was designed using the numerical code TIGER, that allows the physical and chemical properties within the system to vary with time. At the analysis using TIGER, the migration (i.e engineered barrier system, host rock and fault) have to be analysed independently at each region, consequently the huge number of complicated parameter setting have been required. On the other hand, by using numerical code GoldSim, all regions are analyzed synchronously and parameters can be defined at same model. In future, safety analyses of TRU waste package disposal will be carried out according as study of an optimization of nuclear fuel cycle. Therefor, safety assessment model for TRU waste disposal using GoldSim was designed, and calculation results were verified by comparing with the result of TRU-2 report.

JAEA Reports

Development of the next generation reactor analysis code system, MARBLE

Yokoyama, Kenji; Tatsumi, Masahiro*; Hirai, Yasushi*; Hyodo, Hideaki*; Numata, Kazuyuki*; Iwai, Takehiko*; Jin, Tomoyuki*; Hazama, Taira; Nagaya, Yasunobu; Chiba, Go; et al.

JAEA-Data/Code 2010-030, 148 Pages, 2011/03

JAEA-Data-Code-2010-030.pdf:3.23MB

A next generation reactor analysis code system, MARBLE, has been developed. MARBLE is a successor of the fast reactor neutronics analysis code systems, JOINT-FR and SAGEP-FR (conventional system), which were developed for so-called JUPITER standard analysis methods. MARBLE has the equivalent analysis capability to the conventional system. On the other hand, burnup analysis functionality for power reactors as improved compared with the conventional system. In the development of MARBLE, the object oriented technology was adopted. As a result, MARBLE became an assembly of components for building an analysis code (i.e. framework) but not an independent analysis code system which simply receives input and returns output. Furthermore, MARBLE provides some pre-built analysis code systems such as the fast reactor neutronics analysis code system, SCHEME, which corresponds to the conventional code and the fast reactor burnup analysis code system, ORPHEUS.

JAEA Reports

Development of JAEA Sorption Database (JAEA-SDB); Update of data evaluation functions and sorption/QA data

Tachi, Yukio; Suyama, Tadahiro; Ochs, M.*; Ganter, C.*

JAEA-Data/Code 2010-031, 168 Pages, 2011/03

JAEA-Data-Code-2010-031.pdf:6.48MB

JAEA has developed sorption database (SDB) compiling Kd data in buffer material and rock, which is key parameter for performance assessment (PA) of the geological disposal. The present report focuses on developing and updating of the JAEA-SDB as basis of integrated approach for PA-related Kd setting. 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 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, total Kd values in the SDB are about 28,540, and QA/classified Kd data are about 39 % for all Kd data. 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.

JAEA Reports

Monitoring of pore water pressure and groundwater chemistry at MSB-2 and MSB-4 boreholes in the MIU construction site; April, 2009 - March, 2010

Hagiwara, Hiroki; Sai, Masataka*; Takeguchi, Masato*; Horita, Masakuni*; Mizuno, Takashi

JAEA-Data/Code 2010-032, 35 Pages, 2011/03

JAEA-Data-Code-2010-032.pdf:1.8MB

Japan Atomic Energy Agency (JAEA) has been carried out investigation to understand the variation of groundwater chemistry related to the shafts construction of Mizunami Underground Research Laboratory (MIU) at Mizunami City, Gifu prefecture, Japan. This report aimed to compile the data of pore water pressure and groundwater chemistry obtained from surface based boreholes, MSB-2 and MSB-4 boreholes with installed continuous monitoring equipment for multi-interval water pressure (MP system, made by westbay company) between the April 2009 and March 2010. Groundwater sampling and measurement of pore water pressure were conducted once in a month. As the result, we could obtain the data of pore water pressure and groundwater chemistry continuously from 2003 and understand their variation related to the shafts construction in 2009.

JAEA Reports

User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL3 for reactor pressure vessel (Contract research)

Masaki, Koichi; Nishikawa, Hiroyuki*; Osakabe, Kazuya*; Onizawa, Kunio

JAEA-Data/Code 2010-033, 350 Pages, 2011/03

JAEA-Data-Code-2010-033.pdf:5.32MB

The probabilistic fracture mechanics (PFM) analysis code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed in JAEA. The PASCAL code evaluates the conditional probabilities of crack initiation and fracture of a reactor pressure vessel (RPV) under transient conditions such as pressurized thermal shock (PTS). Previous version of PASCAL (PASCAL ver.2) that was released in 2007 has many functions including the evaluation method for an embedded crack and conditional probabilities of crack initiation and fracture of a RPV, PTS transient database, inspection crack detection probability model and others. A generalized analysis method is available on the basis of the development of PASCAL ver.3 and sensitivity analysis results. Graphical user interface (GUI) including a generalized method and some functions of PFM have been also updated for PASCAL3. This report provides the user's manual, examples of analysis and theoretical background of PASCAL ver.3.

JAEA Reports

Kiche; A Simulation tool for kinetics of iodine chemistry in the containment of light water reactors under severe accident conditions (Contract research)

Moriyama, Kiyofumi; Maruyama, Yu; Nakamura, Hideo

JAEA-Data/Code 2010-034, 62 Pages, 2011/03

JAEA-Data-Code-2010-034.pdf:1.43MB

An iodine chemistry simulation tool, Kiche, was developed for analyses of chemical kinetics relevant to iodine volatilization in the containment vessel of light water reactors (LWRs) during a severe accident. It consists of a Fortran code to solve chemical kinetics models, reaction databases written in plain text format, and peripheral tools to convert the reaction databases into Fortran codes. Potential advantages of Kiche are the text format reaction database separated from the code that provides flexibility of the chemistry model, and being a Fortran code relatively easily coupled with other codes such as severe accident analysis codes. This document describes the model, solution method, code structure, and examples of application for simulation of experiments. The appendixes give practical information for the usage of Kiche system.

JAEA Reports

Light water reactor fuel analysis code FEMAXI-7; Models and structure

Suzuki, Motoe; Saito, Hiroaki*; Udagawa, Yutaka

JAEA-Data/Code 2010-035, 361 Pages, 2011/03

JAEA-Data-Code-2010-035.pdf:4.25MB

A light water reactor fuel analysis code FEMAXI-7 has been developed for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. This code is an advanced version which has been produced by incorporating the former version FEMAXI-6 with numerous functional improvements and extensions. In FEMAXI-7, many new models have been added and parameters have been clearly arranged. Also, to facilitate effective maintenance and accessibility of the code, modularization of subroutines and functions have been attained, and quality comment descriptions of variables or physical quantities have been incorporated in the source code. With these advancements, the FEMAXI-7 code has been upgraded to a versatile analytical tool for high burnup fuel behavior. This report describes in detail the design, basic theory and structure, models and numerical method, and improvements and extensions.

JAEA Reports

Study on method of fault zone survey by use of in-situ fault gas (H$$_{2}$$, CO$$_{2}$$, CH$$_{4}$$) measurement (Measurement data set)

Kurosawa, Hideki; Niwa, Masakazu; Ishimaru, Tsuneari; Shimada, Koji

JAEA-Data/Code 2010-036, 199 Pages, 2011/03

JAEA-Data-Code-2010-036.pdf:28.4MB
JAEA-Data-Code-2010-036-appendix(CD-ROM).zip:2.65MB

Research on the influence of fault activity on deep geological environments contributes to the reliability of geological disposal systems for high level radioactive wastes. Measurement of deep-seated gas discharged along faults is proposed as an effective method to understand the extent of influence of fault activity. In this study, in-situ and short-lasting measurement of hydrogen, carbon dioxide and methane gases by use of a portable monitor is tested for prehension of spatial distribution of active faults. The gas measurement data are compiled and recorded on CD-ROM.

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