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Omori, Kazuaki; Shingu, Shinya; Hagiwara, Hiroki; Masuda, Kaoru*; Iizuka, Masatoshi*; Inui, Michiharu*; Iwatsuki, Teruki
JAEA-Data/Code 2013-001, 330 Pages, 2013/05
JAEA-Data-Code-2013-001.pdf:23.85MB
Japan Atomic Energy Agency has been investigated the groundwater chemistry on excavating the underground facilities as part of the Mizunami Underground Research Laboratory (MIU) Project at Mizunami, Gifu, Japan. This report compiles data of the groundwater chemistry obtained at MIU in the fiscal year 2011. In terms of ensuring traceability of data, basic information (e.g. sampling location, sampling date, sampling method, analytical method) and methodology for quality control is described.
Karino, Tomoyuki; Takeuchi, Ryuji
JAEA-Data/Code 2013-002, 45 Pages, 2013/05
JAEA-Data-Code-2013-002.pdf:7.73MB
JAEA-Data-Code-2013-002-appendix(CD-ROM).zip:173.68MB
Tono Regional Hydrogeological Study (RHS) Project is a one of the geoscientific research programme at Tono Geoscience Center (TGC). This project started since April, 1992 and main investigations were finished to March 2004. Since 2005, hydrogeological and hydrochemical monitoring are continued by the existing monitoring system. This paper describes the results of the long term hydro-pressure monitoring from April, 2011 to March, 2012.
Sato, Seiji; Takeda, Masaki; Takeuchi, Ryuji
JAEA-Data/Code 2013-003, 19 Pages, 2013/06
JAEA-Data-Code-2013-003.pdf:2.36MBJAEA-Data-Code-2013-003-appendix(CD-ROM).zip:15.46MB
The Tono Geoscientific Research Unit 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 the calibration of the hydrogeological model. In the subsurface water balance observations, rainfall data and river flow rate have been observed in the Garaishi river and the Hiyoshi river watersheds. The missed data and data error in the monitoring data during the fiscal year 2010 were complemented or corrected, and these data were compiled in data set. Both of the observation data and compiled data are included into the data set, and the data set is recorded on CD-ROM.
Yuguchi, Takashi; Ishibashi, Masayuki; Morikawa, Keita; Kunimaru, Takanori
JAEA-Data/Code 2013-004, 38 Pages, 2013/06
JAEA-Data-Code-2013-004.pdf:15.49MB
Tono Geoscientific Research Unit of Japan Atomic Energy Agency (JAEA) is carrying out the Underground Research Laboratory Project, which is a scientific study revealing the deep geological environment as a basis of research and development for geological disposal of high level radioactive wastes. Nowadays, the project is under the Phase II and Phase III. In the 2011 fiscal year, rock specimens accompanied with grout-filling fracture were collected from -300m Access / Research Gallery of the Mizunami Underground Research Laboratory Construction Site, which were processed into thin sections, and then observed through polarizing microscopy. The grout-filling fracture can be identified as groundwater flow path and thus mass transfer pathway. Investigation methodology and petrological / mineralogical data are basic information for the study of mass transfer in Phase III. This paper presents sampling procedure of rock specimen accompanied with grout-filling fracture and compiles the results of these petrographical observations and analyses.
Suzuki, Motoe; Saito, Hiroaki*; Udagawa, Yutaka; Nagase, Fumihisa
JAEA-Data/Code 2013-005, 382 Pages, 2013/07
JAEA-Data-Code-2013-005.pdf:6.4MB
A light water reactor fuel analysis code FEMAXI-7 has been developed for the purpose of analyzing the fuel behavior in both normal conditions and 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 analyses. This report describes in detail the design, basic theory and structure, models and numerical method, and improvements and extensions.
Yamada, Junya; Seya, Natsumi; Haba, Risa; Muto, Yasunobu; Numari, Hideyuki*; Sato, Naomitsu*; Nemoto, Koji*; Takasaki, Hiroichi*; Shimizu, Takehiko; Takasaki, Koji
JAEA-Data/Code 2013-006, 100 Pages, 2013/06
JAEA-Data-Code-2013-006.pdf:12.04MB
This report presents the results of emergency radiation monitoring, including ambient 
-ray dose rate, atmospheric radioactivity, meteorological observation and estimation of internal exposure resulting from the accident at the Fukushima Daiichi Nuclear Power Plant triggered by the earthquake off the pacific coast of Tohoku on 11th March 2011, conducted by Oarai Research and Development Center (ORDC), Japan Atomic Energy Agency (JAEA) from March to May, 2011. ORDC is located in the central part of Ibaraki prefecture and approximately 130 km southwest of the Fukushima Daiichi Nuclear Power Plant. From around 15th to 21st March, 2011, the ambient -ray dose rate increased and many radioactive nuclides were detected in the atmosphere.
Karino, Tomoyuki; Takeuchi, Ryuji
JAEA-Data/Code 2013-007, 100 Pages, 2013/07
JAEA-Data-Code-2013-007.pdf:7.78MBJAEA-Data-Code-2013-007-appendix(CD-ROM).zip:507.56MB
Mizunami Underground Research Laboratory (MIU) Project has three overlapping phases: Surface-based investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III), with a total duration of 20 years. The main goals of the MIU Project from Phase I through to Phase III are: to establish techniques for investigation, analysis and assessment of the deep geological environment, and to develop a range of engineering for deep underground application. Currently, the project is being carried out under the Phase II. One of the Phase II goals is set to develop and revise models of the geological environment using the investigation results obtained during excavation, and determine and assess the changes in the geological environment in response to excavation. The long term hydro-pressure monitoring has been continued to achieve the Phase II goals. This paper describes the results of the long term hydro-pressure monitoring from April, 2011 to March, 2012.
Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Hoshi, Akiko; Tsuji, Tomoyuki; Higuchi, Hidekazu
JAEA-Data/Code 2013-008, 16 Pages, 2013/11
JAEA-Data-Code-2013-008.pdf:2.41MB
Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data about the radioactivity concentrations which accumulated by the analysis.
Suzuki, Motoe; Saito, Hiroaki*; Udagawa, Yutaka; Nagase, Fumihisa
JAEA-Data/Code 2013-009, 306 Pages, 2013/10
JAEA-Data-Code-2013-009.pdf:5.73MB
A light water reactor fuel analysis code FEMAXI-7 has been developed, as an extended version from the former version FEMAXI-6, for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which are fully disclosed in the code model description published in the form of another JAEA-Data/Code report. The present manual, which is the very counterpart of this description document, gives detailed explanations of files and operation method of FEMAXI-7 code and its related codes, methods of input/output, sample Input/output, methods of source code modification, subroutine structure, and internal variables in a specific manner in order to facilitate users to perform fuel analysis by FEMAXI-7.
Hama, Katsuhiro; Sato, Toshinori; Sasao, Eiji; Iwatsuki, Teruki; Kunimaru, Takanori; Matsuoka, Toshiyuki; Takeuchi, Ryuji; Onoe, Hironori; Mikake, Shinichiro
JAEA-Data/Code 2013-010, 58 Pages, 2013/10
JAEA-Data-Code-2013-010.pdf:14.94MB
JAEA at Tono Geoscience Center is pursuing a geoscientific research and development project namely the Mizunami Underground Research Laboratory (MIU) project in crystalline rock environment to construct scientific and technological basis for geological disposal of High-level Radioactive Waste. The MIU project is planned in three overlapping phases; Surface-based Investigation Phase (Phase I), Construction Phase (Phase II) and Operation Phase (Phase III). Currently, the project is under the Phase II and Phase III. In Phase II, adequacy of geological environment model is evaluated. Applicability and feasibility assessment of various elemental technologies adopted to characterize geological environment in Phase I will be evaluated. Furthermore, from a design, construction and safety assessment point of view, a series of evaluation procedures are organized and Geosynthesis Data Flow Diagram is established. This is the integrated data flow from investigation through modeling and analysis. It proposes the rational combinations of investigation items which make the investigation results reflect the safety assessment and designing. In this sense, Geosynthesis Data Flow Diagram indicates the rational framework, from investigation to modeling and analysis, for achieving individual goals and tasks. This report summarizes the Geosynthesis Data Flow Diagram optimized during Phase II investigation. The Geosynthesis Data Flow Diagram will be revised based on the research progress.
Terada, Atsuhiko; Takegami, Hiroaki; Kamiji, Yu; Hino, Ryutaro
JAEA-Data/Code 2013-011, 53 Pages, 2014/03
JAEA-Data-Code-2013-011.pdf:4.29MB
In the accident of Fukushima Daiichi NPP, the high-level contaminated water processing system with zeolite vessel. is operating for treatment of contaminated water mixed with seawater. A spent KURION zeolite vessel is detached from the water processing system and brought to exclusive storage yards. Although water in the vessel is drained before storage, combustible hydrogen could be produced via radiolysis of water absorbed in the zeolite. An analytical code system available for hydrogen diffusion, burning and explosion, and its impact has been prepared in order to confirm a safe long-term storage method of the vessel. The code system consists of several analytical codes such as general-purpose CFD code FLUENT, deflagration analytical code FLACS and detonation analytical code AUTODYN and interfaces connecting each code. This report presents an outline of analytical code system including interfaces, and introduces preliminary analytical study.
Beppu, Shinji; Karino, Tomoyuki*; Takeuchi, Ryuji
JAEA-Data/Code 2013-012, 43 Pages, 2013/12
JAEA-Data-Code-2013-012.pdf:3.68MBJAEA-Data-Code-2013-012-appendix(CD-ROM).zip:151.23MB
The Regional Hydrogeological Study (RHS) Project is a one of the geoscientific research programme at Tono Geoscience Center (TGC). This project started since April 1992 and main investigations were finished to March 2004. Since 2005, hydrogeological and hydrochemical monitoring have been continued using the existing monitoring system. This paper describes the results of the long term hydro-pressure monitoring from April 2012 to March 2013.
Udagawa, Makoto; Katsuyama, Jinya; Onizawa, Kunio
JAEA-Data/Code 2013-013, 145 Pages, 2013/11
JAEA-Data-Code-2013-013.pdf:4.55MB
As a part of research on the structural integrity assessment for LWR components considering aging degradation, a PFM analysis code PASCAL-NP has been developed. This code evaluates the failure probabilities on a basis of Monte Carlo method caused by PWSCC / NiSCC at dissimilar metal welds and structurally discontinuous components. This PFM analysis code has functions of crack initiation and crack growth calculations for various patterns of crack locations and orientations in a probabilistic manner such as the scatters of material strength, crack growth rate and residual stress distribution, and so on. This code can also evaluate the failure probabilities such as leakage and/or break probabilities of Ni-based alloy welds due to these types of SCC. This report summarizes the failure examples in actual plants and theoretical backgrounds. This one also represents methods to execute program and the case studies using PASCAL-NP code.
Suzuki, Motoe; Saito, Hiroaki*; Udagawa, Yutaka; Amaya, Masaki
JAEA-Data/Code 2013-014, 382 Pages, 2014/03
JAEA-Data-Code-2013-014.pdf:16.36MB
A light water reactor fuel analysis code FEMAXI-7 has been developed as the latest version for the purpose of analyzing the fuel behavior in both normal conditions and anticipated transient conditions. 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. This report is the revised edition of the first one, JAEA-Data/Code 2010-035, which describes in detail the design, basic theory and structure, models and numerical method, and improvements and extensions. The first edition was extended by orderly addition and disposition of explanations of models and organized as this revised edition after three years interval.
Sakatani, Keiichi; Sugaya, Toshikatsu; Nakatani, Takayoshi; Funabashi, Hideyuki
JAEA-Data/Code 2013-015, 63 Pages, 2013/11
JAEA-Data-Code-2013-015.pdf:8.75MB
The safety assessment of the sub-surface disposal system should ensure that calculated dose will be lower than the dose assigned to the scenario in question during the period from now to future. In order to realize the safety disposal, we have developed several assessment tools on the GoldSim platform and calculated doses since 2008, and these assessment tools have been improved reflecting the last view of assessment. This report describes safety functions of the disposal system, idea of nuclide migration, formulas for nuclides migration, formulas of exposure dose and structure of assessment tool for groundwater scenario.
Sato, Seiji; Ogata, Nobuhisa; Takeuchi, Ryuji; Takeda, Masaki
JAEA-Data/Code 2013-016, 50 Pages, 2013/12
JAEA-Data-Code-2013-016.pdf:7.85MBJAEA-Data-Code-2013-016-appendix(DVD-ROM).zip:514.1MB
The Tono Geoscientific Research Unit 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 to estimate precipitation and evapotranspiration have been observed in the Shoba River watershed, the Shoba River model watershed and MIU Construction Site. After missed data and data error in the monitoring data from the fiscal year 2010 to 2011 were complemented or corrected, the data was 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 from Fiscal year 2003 to 2011.
Sato, Seiji; Ogata, Nobuhisa; Takeuchi, Ryuji; Takeda, Masaki
JAEA-Data/Code 2013-017, 24 Pages, 2013/12
JAEA-Data-Code-2013-017.pdf:2.73MBJAEA-Data-Code-2013-017-appendix(CD-ROM).zip:28.79MB
The Tono Geoscientific Research Unit 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 missed data and data error in the monitoring data during the fiscal year 2011 were complemented or corrected, and these data were compiled in data set.
Sawada, Sumiyuki*; Nakayama, Masashi; Ishikawa, Makoto
JAEA-Data/Code 2013-018, 25 Pages, 2013/12
JAEA-Data-Code-2013-018.pdf:3.18MBJAEA-Data-Code-2013-018-appendix(CD-ROM).zip:105.32MB
The Horonobe Underground Research Laboratory (URL) Project has being pursued by the Japan Atomic Energy Agency (JAEA) to enhance the reliability of relevant investigations of the deep geological environment within the host sedimentary formations at Horonobe, northern Hokkaido. Horonobe URL will be excavated three shafts (Ventilation shaft, East shaft and West shaft) connected by three drifts (G.L -140m, G.L -250m and G.L -350m) at the time of completion. In the construction area, the sedimentary rock has spread. And the construction position is located in the stratum boundary of Koetoi formation and the Wakkanai formation. According to the investigation from the ground, existence of the fault with springwater and of the methane separated from groundwater was confirmed. From the viewpoint of the security under construction and the control of the amount of springwater from the URL, pre-grouting was carried out. This report summarizes the construction data of the pre-grouting acquired at the Ventilation Shaft.
Oizumi, Akito; Jin, Tomoyuki*; Yokoyama, Kenji; Ishikawa, Makoto; Kugo, Teruhiko
JAEA-Data/Code 2013-019, 278 Pages, 2014/02
JAEA-Data-Code-2013-019.pdf:13.33MBJAEA-Data-Code-2013-019-appendix-(CD-ROM).zip:114.27MB
In design work for nuclear fuel cycle plants, decommissioning facilities and light water reactors (LWRs), it has been feasible to quantitatively evaluate the uncertainty of fuel burnup characteristics with identifying error sources arising from the analytical modeling or the related physical property such as nuclear data. Owing to the recent improvement of sensitivity analysis method and enhancement of computer capability, this new evaluation technology would be a promising strategy against the current demand for quality assurance, verification & validation (V&V) and accountability. The present report summarizes nuclear-data sensitivity of atomic number densities after burnup for the LWR fuels of UO
and MOX in PWR and BWR. The analysis method is based on the generalized perturbation theory with JENDL-4.0 and a multi-purpose reactor analysis code MARBLE. The present study focuses on 35 fission products and 18 actinides. Sensitivities are calculated with respect to multigroup cross sections, half-lives and fission yields. Electronic files of the sensitivities are stored in a compact disk as a database. Important trends of the sensitivities are presented and their physical mechanisms are discussed. By incorporating the sensitivities with nuclear data covariance and post irradiation examination data, it would be possible to meet the demand for V&V and to break down the uncertainty due to nuclear data into dominant error sources. Thus, the sensitivities can be used to suggest the needs for nuclear data measurements and to extract those for reactor physics experiments in order to make the strategic deliberation of design rationalization.
Sato, Seiji; Ogata, Nobuhisa; Takeuchi, Ryuji; Takeda, Masaki
JAEA-Data/Code 2013-020, 38 Pages, 2014/01
JAEA-Data-Code-2013-020.pdf:12.13MBJAEA-Data-Code-2013-020-appendix(CD-ROM).zip:1.41MB
The MIU Project has three overlapping phases: Surface-based Investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III). The MIU Project has been ongoing the Phase II and started the Phase III in 2010 fiscal year. One of the Phase II goals, which is for the project goal, was set to develop and revise models of the geological environment using the investigation results obtained during underground facilities excavation, and to determine and assess changes in the geological environment in response to excavation. The groundwater inflow monitoring into shafts and research galleries has been continued to achieve the Phase II goals. This document presents the results of the groundwater inflow monitoring from fiscal year 2004 to 2011.
Udagawa, Yutaka; Sugiyama, Tomoyuki; Amaya, Masaki
JAEA-Data/Code 2013-021, 43 Pages, 2014/02
JAEA-Data-Code-2013-021.pdf:2.74MBJAEA-Data-Code-2013-021-appendix(CD-ROM).zip:126.49MB
In order to study the effects of cooling conditions on the boiling heat transfer from the fuel rod surface to the coolant water, RIA-simulating experiments with fresh fuels had been conducted in the nuclear safety research reactor (NSRR) under cooling conditions with subcoolings of 
10 to 80 K, flow velocities of 0 to 3 m/s, pressures of 0.1 to 16 MPa. In addition, pre-irradiated fuels had been subjected to the NSRR experiments under cooling conditions with subcoolings of 80 K, stagnant water, and atmospheric pressure. Out of the NSRR experiments, this report presents the fuel specifications, the test conditions, and the transient records during the pulse operations for the cases that the cladding temperature had been successfully measured. Characteristic parameters such as cladding peak temperatures were extracted from the transient records for summarizing the effects of cooling conditions and pre-irradiation on the heat transfer from the cladding surface.
Inagaki, Daisuke
JAEA-Data/Code 2013-022, 116 Pages, 2014/03
JAEA-Data-Code-2013-022.pdf:8.83MBJAEA-Data-Code-2013-022-appendix(DVD-ROM)-1.zip:4112.42MBJAEA-Data-Code-2013-022-appendix(DVD-ROM)-2.zip:4186.23MBJAEA-Data-Code-2013-022-appendix(DVD-ROM)-3.zip:3175.59MBJAEA-Data-Code-2013-022-appendix(DVD-ROM)-4.zip:3945.48MBJAEA-Data-Code-2013-022-appendix(DVD-ROM)-5.zip:1257.91MB
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 East shaft and the 350 m Gallery.
Beppu, Shinji; Karino, Tomoyuki*; Takeuchi, Ryuji; Ogata, Nobuhisa
JAEA-Data/Code 2013-023, 94 Pages, 2014/03
JAEA-Data-Code-2013-023.pdf:14.94MBJAEA-Data-Code-2013-023-appendix(DVD-ROM).zip:554.56MB
Mizunami Underground Research Laboratory (MIU) Project has three overlapping phases: Surface-based investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III), with a total duration of 20 years. Currently, the project is being carried out under the Phase II and the Phase III. One of the Phase II goals of Project is set to develop and revise models of the geological environment using the investigation results obtained during excavation, and determine and assess the changes in the geological environment in response to excavation. The long term hydro-pressure monitoring has been continued to achieve the Phase II goals. This paper describes the results of the long term hydro-pressure monitoring from April 2012 to March 2013.
Omori, Kazuaki; Shingu, Shinya*; Masuda, Kaoru*; Aosai, Daisuke*; Inui, Michiharu*; Iwatsuki, Teruki
JAEA-Data/Code 2013-024, 284 Pages, 2014/03
JAEA-Data-Code-2013-024.pdf:34.27MB
Japan Atomic Energy Agency has been investigating the groundwater chemistry on excavating the underground facilities as part of the Mizunami Underground research Laboratory (MIU) Project at Mizunami City, Gifu Prefecture, Japan. In this report, we compiled data of groundwater chemistry obtained at the MIU in the fiscal year 2012.
Aihara, Jun; Ueta, Shohei; Nakagawa, Shigeaki; Sawa, Kazuhiro; Ohashi, Hirofumi; Tachibana, Yukio
JAEA-Data/Code 2013-025, 64 Pages, 2014/03
JAEA-Data-Code-2013-025.pdf:2.54MB
FORNAX-A is a calculation code for amount of fission product (FP) released from fuel rods of pin-in-type high temperature gas-cooled reactors (HTGRs). This report is for explanation of outline and basic formulae of FORNAX-A code. FORNAX-A is based on Fick's laws of diffusion and can calculate FP release amount from fuel rod under normal operation and accidents without failure (including oxidation) of graphite sleeves and fuel compacts and without melting of fuel kernel, for example, stopping fission and increase in temperature.