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JAEA Reports

Improvement of HEINPUT code for estimating the late somatic and genetic effects induced by radiation exposure

Takahara, Shogo; Homma, Toshimitsu; Nishimura, Yuki*

JAEA-Data/Code 2009-001, 83 Pages, 2009/04

JAEA-Data-Code-2009-001.pdf:13.36MB

We have carried out improvement of HEINPUT code for estimating the late somatic and genetic effects induced by radiation exposure. HEINPUT code is one of the preprocessor codes for probabilistic accident consequence assessment code OSCAAR, and calculates the input data related to the late somatic and genetic effects. HEINPUT code currently uses a model which was submitted by U.S. Nuclear Regulatory Commission (USNRC) revised by NUREG/CR-4214 Rev. 2 (USNRC), 1993. In this report, we improve HEINPUT code and make not only NUREG model but also EPA model (EPA, 1999) estimate the late somatic and genetic effects. In addition, we have created a graphical user interface (GUI) for the purpose of publication of this code and development of risk assessment associated with radiation exposure.

JAEA Reports

SWAT3.1; The Integrated burnup code system driving continuous energy Monte Carlo codes MVP and MCNP

Suyama, Kenya; Mochizuki, Hiroki*; Takada, Tomoyuki*; Ryufuku, Susumu*; Okuno, Hiroshi; Murazaki, Minoru; Okubo, Kiyoshi

JAEA-Data/Code 2009-002, 124 Pages, 2009/05

JAEA-Data-Code-2009-002.pdf:14.09MB

Integrated burnup calculation code system SWAT is a system that combines neutronics calculation code SRAC widely used in Japan and point burnup calculation code ORIGEN2. It has been used to evaluate the composition of the uranium, plutonium, minor actinide and the fission products in the spent nuclear fuel. Because of the ability to treat the arbitrary fuel geometry and no requirement of generating the effective cross section data, there is a great advantage to introduce continuous energy Monte Carlo Code into the burnup calculation code. Based on this idea, the integrated burnup calculation code system SWAT3.1 was developed by combining the continuous energy Monte Carlo code MVP and MCNP and ORIGEN2. This report describes the outline, input data instruction and several example of the calculation.

JAEA Reports

Database on soil-to-plant transfer factors for the safety assessment of geological disposal (Contract research)

Ochiai, Toru; Takeda, Seiji; Kimura, Hideo

JAEA-Data/Code 2009-003, 62 Pages, 2009/06

JAEA-Data-Code-2009-003.pdf:5.46MB

The objective of this study is to estimate the uncertainties on the soil-to-plant transfer factor in the safety assessment. The transfer factors for radionuclides used in the safety assessment were determined based on the results of statistical analysis for transfer factor data collected form literature survey and of comparison with the data published by IAEA. This report provides the determined values of the transfer factor, the process and grounds of determining them, and collected data of transfer factor as database.

JAEA Reports

Activity report for feasibility study on PKI authentication method with IC card in Authentication System Sub Group of J-PARC Information System Group

Teshima, Naoya; Aoyagi, Tetsuo; Hashimoto, Kiyoharu*; Manabe, Atsushi*; Yuasa, Fukuko*; Nakajima, Norihiro

JAEA-Data/Code 2009-004, 24 Pages, 2009/06

JAEA-Data-Code-2009-004.pdf:1.65MB

The authentication System Group of J-PARC Information System Group carried out the feasibility study about PKI authentication method that used IC card. Its purpose was that we validated its practical utility to choose an authentication method to adjust a security level desired at the information system of J-PARC. As a target of the feasibility studies, we chose following four validation items. (1) "The EAP-TLS wireless LAN authentication method" (2) "The Web-SSL client authentication method when accessed via SSL-VPN device" (3) "The PKI authentication method that used IC card stored the certificate which issued by NAREGI-CA software. (4) "The PKI authentication method that used Dual card type FeliCa". We established validation point for each validation item, and carried out it. So, we got the results and useful information. This report is that we organized a validation procedure, result and knowledge that we got by feasibility studies.

JAEA Reports

Skyshine dose calculation code system SKYOSD for operational scenario of radioactive waste disposal

Watanabe, Masatoshi; Takeda, Seiji; Kimura, Hideo

JAEA-Data/Code 2009-005, 18 Pages, 2009/06

JAEA-Data-Code-2009-005.pdf:2.79MB

The shyshine dose to the public at the site boundary of radioactive waste disposal facility has been calculated for the operational scenario which is one of the scenarios for assessing the radionuclide concentration limits for low-level radioactive wastes. The skyshine dose was calculated with the point kernel method in the previous assessment. A computer code system, SKYOSD, employs more rigorous transport equation than before. The SKYOSD stores a one-dimensional transport calculation code ANISN-JR to calculate photon fluence rate on the disposal facility, and a two-dimensional transport calculation code DOT3.5 to calculate dose from a point kernel predetermined on the facility. This report provides a description for the structure of the SKYOSD code system and the parameter setting for skyshine dose calculation.

JAEA Reports

Calculation of the kinetic parameters for homogeneous fuel systems (MOX powder with zinc stearate and plutonium nitrate solution)

Sato, Shohei; Okuno, Hiroshi

JAEA-Data/Code 2009-006, 43 Pages, 2009/07

JAEA-Data-Code-2009-006.pdf:6.53MB

This report represents the kinetic parameters for homogeneous fuel systems obtained in the cooperative study with the Institut de Radioprotection et de Surete Nucleaire (IRSN) in France. The subject fuels for calculation are MOX powder mixed with zinc stearate and plutonium nitrate solution. The TWODANT code is utilized with 17 energy groups JENDL3.3 cross section collapsed by SRAC. As a result of the calculations, it was found that (1) The kinetic parameters of MOX powder is dependent on plutonium enrichment and the fraction of hydrogen, and is not dependent on the density of MOX powder and the fuel height except for the neutron lifetime, despite the kind of fuel system, (2) The kinetic parameters of plutonium nitrate solution depend on the concentration of plutonium; the temperature coefficient of which plutonium concentration is below 19g/l is positive.

JAEA Reports

Gas measurements of ground surface part and shallow boreholes in the Hokushin area and the Kaishin area, Horonobe, northern Hokkaido

Abe, Hironobu; Takahashi, Kazuharu*; Fujishima, Atsushi

JAEA-Data/Code 2009-007, 35 Pages, 2009/07

JAEA-Data-Code-2009-007.pdf:6.85MB

We are carring out a geological survey to understand important geological structure as geological heterogeneity and migration pathway of material in the bedrock of around the URL area. This report summarizes method and the result of gas measurements, carried out in the Hokushin area and the Suwanosawa area, a period of the FY 2002 to FY 2006. We have investigated gas concentrations of CH$$_{4}$$ and CO$$_{2}$$ (methane and carbon dioxide) along the Omagari fault, and discussed correlations between the gas concentrations and the Omagari fault. The high amount of CO$$_{2}$$ gas concentration were observed around the Omagari Fault.

JAEA Reports

Development of Radiation Dose Assessment System for Radiation Accident (RADARAC)

Takahashi, Fumiaki; Shigemori, Yuji*; Seki, Akiyuki

JAEA-Data/Code 2009-008, 127 Pages, 2009/07

JAEA-Data-Code-2009-008.pdf:10.5MB

A radiation transport calculation can derive dose distribution in a heavily exposed person for the medical treatment at the case of an accident. Since the accident cannot be prospected, many complicated procedures are needed to make the input file soon after the accident and to inform radiation dose based upon the output files with much information concerning the calculation. Thus, ($underline{Ra}$)diation ($underline{D}$)ose ($underline{A}$)ssessment system for ($underline{R}$)adiation ($underline{Ac}$)cident (RADARAC) was developed to derive effectively radiation dose by the MCNPX or the MCNP code. RADARAC consists of RADARAC_INPUT and RADARAC_DOSE. A user can interactively set up necessary resources to make input files with three programs in RADARAC_INPUT. The results of radiation doses are indicated with tables, graphs and figures depicting dose distribution by RADARAC_DOSE. It is confirmed that RADARAC can make input files with a few thousand lines and indicate more than 20,000 data dose within a few minutes.

JAEA Reports

Study and design of safety assessment model based on H12 reference case using GoldSim

Nakajima, Kunihiko*; Koo, Shigeru*; Ebina, Takanori*; Ebashi, Takeshi; Inagaki, Manabu

JAEA-Data/Code 2009-009, 62 Pages, 2009/07

JAEA-Data-Code-2009-009.pdf:19.19MB

Reference case of safety assessment analysis at the H12 report was calculated using the numerical code MESHNOTE and MATRICS mainly. On the other hand, recently general simulation software witch has a character of object-oriented is globally used and the numerical code GoldSim is typical software. After the H12 report, probability theory analysis and sensitivity analysis using GoldSim have carried out by statistical method for the purpose of following up safety assessment analysis at the H12 report. On this report, details of the method for the model design using GoldSim are summarized, and to confirm calculation reproducibility, verification between the H12 report and GoldSim results were carried out. And the guide book of calculation method using GoldSim is maintained for other investigators at JAEA who want to calculate reference case on the H12 report. In the future, application resources on this report will be able to upgrade probability theory analysis and other conceptual models.

JAEA Reports

Second version of data collection part of nuclear criticality safety handbook (Contract research)

Okuno, Hiroshi; Suyama, Kenya; Tonoike, Kotaro; Yamane, Yuichi; Yamamoto, Toshihiro; Miyoshi, Yoshinori; Uchiyama, Gunzo

JAEA-Data/Code 2009-010, 175 Pages, 2009/08

JAEA-Data-Code-2009-010.pdf:13.1MB
JAEA-Data-Code-2009-010(errata).pdf:0.11MB

The report revised the Data Collection part of Nuclear Criticality Safety Handbook, which was published in 1988. This second version provided criticality data on homogeneous U-H$$_{2}$$O and UF$$_{6}$$-HF, which were not cited in the previous version, and increased those data on the medium-enriched uranium fuels. Calculations were performed mainly with the Continuous-Energy Monte Carlo Criticality Calculation Code, MVP, and the Japanese Evaluated Nuclear Data Library, JENDL-3 Revision 2, JENDL-3.2, both of which were developed at the late Japan Atomic Energy Research Institute (JAERI). Data on atomic number densities of actinide metal and oxide were additionally supplied, and nuclide compositions of irradiated fuels were improved from the first version. One million histories of neutrons were followed in benchmark calculations of critical experiments and in calculations of single-unit criticality data, i.e., critical mass, volume, dimensions, etc., to attain almost ten times higher precision than the first version.

JAEA Reports

FEP database for scenario construction on groundwater migration in safety assessment for a geological disposal of high-level radioactive waste (Contract research)

Kanzaki, Yutaka; Takeda, Seiji; Kimura, Hideo

JAEA-Data/Code 2009-011, 90 Pages, 2009/09

JAEA-Data-Code-2009-011.pdf:4.76MB

Scenario description is the first and essential step in the safety assessment of geologic disposal of radioactive waste. Scenarios are constructed considering factors that are likely to affect long-term safety of disposal. Recent safety assessment studies employ the "FEP" approach, where scenarios are constructed based on comprehensive information on features, events and processes (FEPs) occurring in the disposal system. We began choosing FEPs from the internationally common OECD/NEA FEP database. Then we added scientific and technical information on the chosen FEPs obtained through comprehensive. The correlations were scrutinized to select finally critical safety correlations, which became elements integrated to safety assessment scenarios. This report provides aforementioned FEP-related database and illustrates the scenario construction procedure for the groundwater transporting radionuclide scenario.

JAEA Reports

Development of a framework for the neutronics analysis system for next generation, 3

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

JAEA-Data/Code 2009-012, 208 Pages, 2010/02

JAEA-Data-Code-2009-012.pdf:11.28MB

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, we examined in detail the existing design and implementation of ZPPR critical experiment analysis database followed by unification of models within the framework of the next-generation analysis system by extending to various critical experiment analysis. Furthermore, we examined requirements for functions of analysis results correction which is indispensable for critical analysis system, and designed and implemented an analysis system for various critical experiments including ZPPR.

JAEA Reports

Critical assembly simulator with the one-point reactor kinetics (CASIM)

Tonoike, Kotaro; Uchiyama, Gunzo

JAEA-Data/Code 2009-013, 51 Pages, 2009/11

JAEA-Data-Code-2009-013.pdf:13.4MB

A simulator has been developed to help, in a lecture meeting for instance, public understanding of fission chain reactions or basic nuclear reactor operations. The simulator has the simple one-point reactor kinetics model with no reactivity feedback, which, therefore, models a critical assembly operated with very low power in a room temperature, instead of a power reactor or a research reactor whose core temperature is raised by the energy of fission chain reaction. Thus, the simulator has been named as "CASIM: Critical Assembly SIMulator". CASIM has only two operation items: the neutron source insertion/extraction, and the reactivity control of one kind. It has indications of the neutron source position and the neutron level (the power) in linear and logarithmic scales. No reactor period meter is equipped. The delayed neutron fraction $$beta$$, as a parameter of the simulated kinetics, is selectable from 0.74% and 0.37%. The former is for a uranium fuel and the latter is for a plutonium fuel. Hypothetical situations such as $$beta$$=0.19% or "Delayed Neutron: None" are also options to demonstrate the extreme conditions manually uncontrollable. CASIM runs on a standard Windows personal computer and has been used in lecture meetings such as a seminar held in the Kansai Photon Science Institute.

JAEA Reports

Calculation of the estimated criticality lower limit multiplication factor of MOX fuel systems based on the evaluation of calculation errors dependent on plutonium-240 isotopic fraction

Sato, Shohei; Okuno, Hiroshi

JAEA-Data/Code 2009-014, 19 Pages, 2009/11

JAEA-Data-Code-2009-014.pdf:3.03MB

The estimated criticality lower limit multiplication factor (hereafter, ECLLMF) is the upper limit of the neutron multiplication factor where the system may be judged subcritical through the calculation results of the same criticality calculation system applied to analogous fuel systems to be evaluated. Aiming to establish an effective method to find the rational ECLLMF of mixed uranium and plutonium oxide (MOX) fuel systems, this report investigated the classification of the critical experiments for the statistical processing, and evaluated the calculation errors with considering the dependence on $$^{240}$$Pu isotopic fraction within the classified experiments. In this evaluation, the criticality calculation code MVP and the evaluated nuclear data library JENDL-3.3 library were utilized, and the criticality experiments with MOX fuels registered in the international criticality safety benchmark evaluation project (ICSBEP) handbook were adopted. It was found that the dependency of the benchmark calculation results on the $$^{240}$$Pu isotopic fraction was enhanced by introducing a new fuel class: "dual heterogeneous fuel systems." As a result of this classification and error evaluation, it was confirmed that the calculated values of all the ECLLMFs were below the benchmark calculation results, and that the value of the ECLLMF was high compared with that obtained with the traditional method.

JAEA Reports

Collection of URL measurement data in 2008 at the Horonobe Underground Research Laboratory Project

Sano, Michiaki; Ishii, Eiichi; Niinuma, Hiroaki; Fujikawa, Daisuke; Sanada, Hiroyuki; Hiraga, Naoto; Tsusaka, Kimikazu; Yamasaki, Masanao*

JAEA-Data/Code 2009-015, 142 Pages, 2009/11

JAEA-Data-Code-2009-015.pdf:41.84MB

In the Horonobe Underground 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 Ventilation Shaft (GL -161m $$sim$$ -250m), the East Shaft (GL -110m $$sim$$ -140m) and the 140m drift.

JAEA Reports

Sophistication of burnup analysis system for fast reactor

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

JAEA-Data/Code 2009-016, 100 Pages, 2010/02

JAEA-Data-Code-2009-016.pdf:8.18MB

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 the present study, we implemented functions for cell calculations and burnup calculations. With this, whole steps in analysis can be carried out with only this system. In addition, we modified the specification of user input to improve the convenience of this system. Since implementations being done so far had some bottlenecks to be resolved; we have realized the improvement on efficiency and amount of memory usage with modification on actual implementation.

JAEA Reports

Monitoring of pore water pressure and groundwater chemistry at MSB-2 and MSB-4 boreholes; April, 2006 - March, 2007

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

JAEA-Data/Code 2009-017, 200 Pages, 2010/01

JAEA-Data-Code-2009-017.pdf:10.43MB

Japan Atomic Energy Agency (JAEA) have 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 shows 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, 2006 to March, 2007.

JAEA Reports

Radiation resistance of polymer materials; Degradation evaluation by accelerated testing for application condition

Seguchi, Tadao*; Sorimachi, Masami*; Tamura, Kiyotoshi

JAEA-Data/Code 2009-018, 123 Pages, 2010/02

JAEA-Data-Code-2009-018.pdf:23.94MB

The radiation resistance of 25 type polymer materials as plastics and rubbers applied in practical environments was evaluated by the accelerated testing of $$gamma$$-ray irradiation under oxygen pressure, and compared with the radiation resistance determined from the traditional testing by irradiation with a high dose rate in air. The polymer materials were formulated to be similar or equivalent to practical materials, and the most of formulation (chemical compounds and quantities) were disclosed. For all materials, the tensile properties (elongation at break, ultimate strength, 100% or 200% modulus), electric resistivity, gel-fraction, and density were measured after irradiation in oxidation conditions and non-oxidation conditions. The data of relations between each properties and total dose at various conditions were compiled, and the relations among the changes of mechanical properties, electrical properties, and radiation induced chemical reactions were discussed.

JAEA Reports

Development of clearance level verification evaluation system, 1; Fabrication of program for selection of nuclides for measurement and assessment

Tachibana, Mitsuo; Ishigami, Tsutomu

JAEA-Data/Code 2009-019, 52 Pages, 2010/02

JAEA-Data-Code-2009-019.pdf:10.09MB

Clearance activities for a large amount of waste with decommissioning of nuclear reactor facilities have been planned in the JAEA. To improve efficiency of clearance activities, the CLEVES has been developed to support safe and secure clearance of wastes. Program for selection of nuclides for meas. and assessment was fabricated for selecting nuclides to be evaluated based on relative importance measure for nuclides according to contamination source or contamination property of clearance objects. In addition, case studies ware carried out by using the program based on data concerning actual clearance activities in the JAEA. As a result, it has been found to be able to select nuclides for meas. and assessment safely by the individual method which evaluates relative importance measure of each contamination source, when it is difficult to analyze evaluated activity of nuclide. In this report, outline of the program was described.

JAEA Reports

Establishment of database for Japan Sea parameters on marine environment and radioactivity (JASPER), 2; Radiocarbon and oceanographic properties

Otosaka, Shigeyoshi; Suzuki, Takashi; Tanaka, Takayuki; Ito, Toshimichi; Kobayashi, Takuya; Kawamura, Hideyuki; Minakawa, Masayuki*; Aramaki, Takafumi*; Senju, Tomoharu*; Togawa, Orihiko

JAEA-Data/Code 2009-020, 27 Pages, 2010/02

JAEA-Data-Code-2009-020.pdf:2.45MB

The database for the Japan Sea parameters on marine environment and radionuclides (JASPER) has been established by the Japan Atomic Energy Agency as a product of the Japan Sea Expeditions. By the previous version of the database, data for representative anthropogenic radionuclides were opened to public. And now, data for radiocarbon and fundamental oceanographic properties (salinity, temperature, dissolved oxygen) including nutrients (silicate, phosphate, nitrate and nitrite) are released as the second volume of the database. In the second volume, 20,398 data records are stored including 2,695 data for temperature, 2,883 data for salinity, 2,109 data for dissolved oxygen, 11,051 data for the nutrients, and 1,660 data for radiocarbon. The database will be a strong tool for the continuous monitoring for contamination by anthropogenic radionuclides, studies on biogeochemical cycle, and development and validation of models for numerical simulations in the sea.

JAEA Reports

Evaluating and categorizing the reliability of distribution coefficient values in the sorption database, 3

Ochs, M.*; Suyama, Tadahiro; Kunze, S.*; Tachi, Yukio; Yui, Mikazu

JAEA-Data/Code 2009-021, 144 Pages, 2010/02

JAEA-Data-Code-2009-021.pdf:4.88MB

Sorption of radionuclides in bentonites and rocks is one of the key processes in the safe geological disposal of radioactive waste. Japan Atomic Energy Agency (JAEA) has developed sorption database (JAEA-SDB) which includes extensive compilation of sorption Kd data by batch experiments, extracted from published literatures. In this report, the QA/classification of selected entries in the JAEA-SDB, focusing granite rocks which are related to reference systems in H12 PA and possible applications in the context of URL activities, and Fe-oxide/hydroxide, Al-oxide/hydroxide existing widely in geological environment, was done following the approach/guideline defined in our previous report. As a result, the reliability of 1,373 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

Development of overpack database

Taniguchi, Naoki; Nakamura, Ario*

JAEA-Data/Code 2009-022, 56 Pages, 2010/03

JAEA-Data-Code-2009-022.pdf:14.6MB

In geological disposal of high-level radioactive waste, overpack is required to prevent vitrified waste from the contacting groundwater with during a certain period of time. At present, the period is defined as 1000 years for complete containment and developments of technologies for design, manufacturing and quality assurance and researches for improving long-term performance have been carried out. Each R&D results have been published as a reports or journal papers by each individual institute. However, it is necessary to integrate these results so as to develop a practical knowledge base that would be useful for design of an overpack for a specific repository site, establishment of the codes and standards or other general purposes. Accordingly, we have been developing a database, which integrate R&D results on design concepts of overpack, technologies for design and manufactureing, test data of the characteristics as an overpack and so on. The basic structure of the database has already been completed last year. At present, two main data; corrosion data and the test data of overpack welding and inspections, are being summarized and imported into the database system. In this report, contents of the table were discussed and the datasets that have already been imported into the database system were appended.

JAEA Reports

Analysis of the radioactivity concentrations in asphalt- or cement-solidified products generated from research facilities

Hoshi, Akiko; Kameo, Yutaka; Katayama, Atsushi; Sakai, Akihiro; Tsuji, Tomoyuki; Nakashima, Mikio; Kihara, Shinji; Takahashi, Kuniaki

JAEA-Data/Code 2009-023, 84 Pages, 2010/03

JAEA-Data-Code-2009-023.pdf:12.81MB

In order to establish the practical evaluation methods such as scaling factor method to determine the radioactivity concentrations of the important nuclides for safety assessment of disposal of radioactive wastes, we analyzed low-level radioactive liquid waste (56 samples), which is generated from various research facilities at Nuclear Science Research Institute from FY1998 to FY2007 and accumulated the radioactivity concentrations data (563 data) of the 17 important nuclides. We investigated the correlation of the radioactivity concentrations of the important nuclides with the "Key nuclides ($$^{60}$$Co or $$^{137}$$Cs)". In present paper, the radioactivity concentrations data of the 17 important nuclides and the results of the correlation of the radioactivity concentrations are summarized for the data to establish the practical evaluation methods to determine the radioactivity concentrations in asphalt-solidified or cement-solidified products.

JAEA Reports

JAEA thermodynamic database for performance assessment of geological disposal of high-level radioactive and TRU wastes

Kitamura, Akira; Fujiwara, Kenso; Doi, Reisuke; Yoshida, Yasushi*; Mihara, Morihiro; Terashima, Motoki; Yui, Mikazu

JAEA-Data/Code 2009-024, 84 Pages, 2010/03

JAEA-Data-Code-2009-024.pdf:2.84MB

A thermodynamic database was established to develop a thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Twenty-four elements (actinides, fission products and their daughters) which are of importance for the performance assessment of geological disposal have been selected. The fundamental plan was in principle based on the guidelines established by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Additional unique guidelines were established due to a requirement from the performance assessment to select tentative thermodynamic values obtained from chemical analogues and/or models for elements with insufficient thermodynamic values. Selected thermodynamic data were compiled for geochemical calculation programs.

JAEA Reports

User's manuals of probabilistic fracture mechanics analysis code for aged piping, PASCAL-SP

Ito, Hiroto; Kato, Daisuke*; Osakabe, Kazuya*; Nishikawa, Hiroyuki; Onizawa, Kunio

JAEA-Data/Code 2009-025, 135 Pages, 2010/03

JAEA-Data-Code-2009-025.pdf:17.49MB

As a part of the aging and structural integrity research for LWR components, new PFM (Probabilistic Fracture Mechanics) analysis code PASCAL-SP (PFM Analysis of Structural Components in Aging LWR - Stress Corrosion Cracking at Welded Joints of Piping) has been developed. This code evaluates the failure probabilities at welding lines of aged piping by a Monte Carlo method. PASCAL-SP treats stress corrosion cracking (SCC) in piping, including approaches of NISA and JSME FFS Code. The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the latest knowledge in the SCC assessment and fracture criteria of piping. In addition, the accuracy of flaw detection and sizing at in-service inspection and residual stress distribution were modeled based on experimental data and introduced into PASCAL-SP. This report provides the user's manual and theoretical background of the code.

JAEA Reports

Development of mechanical analysis code (MACBECE) for TRU waste disposal

Mihara, Morihiro; Sato, Nobuyuki; Ono, Shintaro*; Morikawa, Seiji*

JAEA-Data/Code 2009-026, 114 Pages, 2010/03

JAEA-Data-Code-2009-026.pdf:15.21MB

This report shows the capability, incorporated mechanical model and sample calculation of MACBECE. MACBECE incorporated the non-liner elastic model for cement-based material, the elasto- viscoplastic model considering swelling of bentonite-based material and the visco-elastic model reported by Okubo for host-rock. Furthermore, MACBECE can consider chemical transition of bentonite-based and cement-based materials.

JAEA Reports

Annual data compilation of the water balance observation in the regional hydrogeological study project (RHS Project); Monitoring data from the fiscal year 2004 to 2007

Sato, Atsuya; Takeuchi, Ryuji

JAEA-Data/Code 2009-027, 27 Pages, 2010/03

JAEA-Data-Code-2009-027.pdf:2.56MB

At the Tono Geoscience Center, the subsurface water balance observation has been carried out in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for the calibration of the hydrogeological model. The missed data and data error in the monitoring data from the fiscal year 2004 to 2007 were complemented or corrected the data was compiled in data set.

JAEA Reports

Annual data compilation of the water balance observation in the Mizunami Underground Research Laboratory Project (MIU Project); From the fiscal year 2004 to 2007

Sato, Atsuya; Takeuchi, Ryuji

JAEA-Data/Code 2009-028, 43 Pages, 2010/03

JAEA-Data-Code-2009-028.pdf:3.03MB

At the Tono Geoscience Center, the subsurface water balance observation has been carried out in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for the calibration of the hydrogeological model. After missed data and data error in the monitoring data from the fiscal year 2004 to 2007 were complemented or corrected, the data was compiled in data set.

JAEA Reports

Development of diffusion database of buffer materials and rocks; Expansion and application method of foreign buffer materials

Tochigi, Yoshikatsu; Tachi, Yukio

JAEA-Data/Code 2009-029, 39 Pages, 2010/03

JAEA-Data-Code-2009-029.pdf:3.33MB

Japan Atomic Energy Agency (JAEA) has been developing database of diffusion parameters in buffer material (bentonite) and rock, which are key parameters for safety assessment of the geological disposal. JAEA is continuing development and updating such as parameter estimation, finding data trend, examining related information concerning reliability have been carried on to apply the database in parameter setting for safety assessment. As the result of data addition, total data count of effective diffusion coefficient is 2,020 (599 for measured value) and that of apparent diffusion coefficient is 1,747 (measured value). As an example of practical use of the improved database, the example of evaluation for the plot of a diffusion coefficient vs. dry and partial smectite density was discussed. As a result of introducing partial smectite density for database update, domestic and foreign bentonites are normalized on same index and compared each other on the same plot of measured data.

JAEA Reports

The Data of the long term hydro-pressure monitoring on Mizunami Underground Research Laboratory Project from fiscal year 2005 to fiscal year 2008

Keya, Hiromichi; Takeuchi, Ryuji

JAEA-Data/Code 2009-030, 74 Pages, 2010/03

JAEA-Data-Code-2009-030.pdf:5.76MB

Tono Geoscience Center (TGC) of Japan Atomic Energy Agency (JAEA) is being performed Mizunami Underground Research Laboratory (MIU) Project. The MIU Project is under the Construction phase (Phase II). One of the Phase II goals was set to develop and revise models of the geological environment using the investigation results obtained during excavation, and determine and assess changes in the geological environment in response to excavation. The hydro-pressure long term monitoring has been continued to achieve the Phase II goals. This document presents the results of the hydro-pressure long term monitoring from fiscal year 2005 to fiscal year 2008.

JAEA Reports

The Data of the long term hydro-pressure monitoring on Tono Regional Hydrogeological Study Project from fiscal year 2005 to fiscal year 2008

Keya, Hiromichi; Takeuchi, Ryuji

JAEA-Data/Code 2009-031, 38 Pages, 2010/03

JAEA-Data-Code-2009-031.pdf:2.5MB

Tono Geoscience Center (TGC) of Japan Atomic Energy Agency (JAEA) has been conducting a wide range of geoscientific research in order to build firm scientific and technological basis for geological disposal of nuclear wastes, in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in fractured crystalline rock. One of the geoscientific research programme is a Regional Hydrogeological Study (RHS) project in the Tono region, central Japan. This project started in fiscal year 1992 and main investigations finished in fiscal year 2004. After the main investigations, hydrogeological or hydrochemical long term monitoring are continued by the existing monitoring system. This document presents the results of the hydro-pressure long term monitoring from fiscal year 2005 to fiscal year 2008.

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