Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Dei, Shuntaro; Mochizuki, Akihito
JAEA-Data/Code 2022-001, 29 Pages, 2022/06
JAEA-Data-Code-2022-001.pdf:3.03MB
JAEA-Data-Code-2022-001-appendix(CD-ROM).zip:2.06MB
Japan Atomic Energy Agency had been conducting "geoscientific study" and "research and development on geological disposal" in the Horonobe Underground Research Laboratory (URL) for safe geological disposal of high-level radioactive waste. In the Horonobe underground research project for FY 2020 and subsequent years, the pressure and water quality of groundwater have been continuously monitored using monitoring systems in order to obtain the data necessary for conducting the remaining important issues which were deduced from summarization of important issues between 2015-2019. This report presents pressure and physicochemical parameters (temperature, pH, electrical conductivity, oxidation-reduction potential and dissolved oxygen concentration) of groundwater which have been obtained from April 2020 to the end of March 2021 by the monitoring systems installed at the 140 m, 250 m and 350 m gallery.
Honda, Norihisa; Dei, Shuntaro; Ishii, Eiichi
JAEA-Data/Code 2022-002, 37 Pages, 2022/06
JAEA-Data-Code-2022-002.pdf:2.85MBJAEA-Data-Code-2022-002-appendix(CD-ROM).zip:5.68MB
Long-term monitoring of pore pressure/groundwater level has been performed at the deep boreholes HDB-1-11 and PB-V01 and seven shallow boreholes in the Horonobe Underground Research Laboratory Project. This report summarizes the results obtained from the starts of monitoring to March 2021.
Aihara, Jun
JAEA-Data/Code 2022-003, 77 Pages, 2022/06
JAEA-Data-Code-2022-003.pdf:1.62MB
FORNAX-A1.0 is a calculation code for amount of fission product (FP) released from fuel rods of pin-in-type high temperature gas-cooled reactors (HTGRs). FORNAX-A1.0 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 and/or failure fraction of coated fuel particles. This report is for explanation of outline, basic formulae and numerical analysis method of FORNAX-A1.0 code.
Tsuchida, Daiki; Mitsukai, Akina; Aono, Ryuji; Haraga, Tomoko; Ishimori, Kenichiro; Kameo, Yutaka
JAEA-Data/Code 2022-004, 87 Pages, 2022/07
JAEA-Data-Code-2022-004.pdf:6.73MB
Radioactive wastes generated from nuclear research facilities in Japan Atomic Energy Agency are planning to be buried in the near surface disposal field. Therefore, it is required to establish the method to evaluate the radioactivity concentrations of radioactive wastes until by the beginning of disposal. In order to contribute to this work, we collected and analyzed samples generated from JPDR, JRR-3 and JRR-4. In this report, radioactivity concentrations of 20 radionuclides (
H, 
C, 
Cl, 
Co, 
Ni, 
Sr, 
Nb, 
Tc, 
Ag, 
I, 
Cs, 
Eu, 
Eu, 
U, 
U, Pu, 
Pu, 
Am, 
Cm) were determined based on radiochemical analysis and summarized as basic data for the study of evaluation method of radioactive concentration.
Otsuka, Naohiko*; Iwamoto, Osamu
JAEA-Data/Code 2022-005, 102 Pages, 2022/10
JAEA-Data-Code-2022-005.pdf:2.18MBJAEA-Data-Code-2022-005-appendix(CD-ROM).zip:3.85MB
The neutron-induced fission cross sections were simultaneously evaluated for the JENDL-5 library for 
U and 
Pu from 10 keV to 200 MeV and for U and 
Pu from 100 keV to 200 MeV. Evaluation was performed by least-squares fitting of Schmittroth's roof function to the logarithms of the experimental cross sections and cross section ratios in the EXFOR library. A simultaneous evaluation code SOK was used with its extension to data in arbitrary unit. This report describes (1) construction of the experimental database, (2) selection of data points from TUD-KRI collaboration, (3) comparison with the evaluated cross sections in recent major libraries, and (4) impact of the 
U datasets published in 1970s.
Takamizawa, Hisashi; Lu, K.; Katsuyama, Jinya; Masaki, Koichi*; Miyamoto, Yuhei*; Li, Y.
JAEA-Data/Code 2022-006, 221 Pages, 2023/02
JAEA-Data-Code-2022-006.pdf:4.79MB
As a part of the structural integrity assessment research for aging light water reactor (LWR) components, a probabilistic fracture mechanics (PFM) analysis code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed in Japan Atomic Energy Agency. The PASCAL code can evaluate failure probabilities and failure frequencies of core region in reactor pressure vessel (RPV) under transients by considering the uncertainties of influential parameters. The continuous development of the code aims to improve the reliability by introducing the analysis methodologies and functions base on the state-of-the-art knowledge in fracture mechanics and domestic data. In the first version of PASCAL, which was released in FY2000, the basic framework was developed for analyzing failure probabilities considering pressurized thermal shock events for RPVs in pressurized water reactors (PWRs). In PASCAL Ver. 2 released in FY 2006, analysis functions including the evaluation methods for embedded cracks and crack detection probability models for inspection were introduced. In PASCAL Ver. 3 released in FY 2010, functions considering weld-overlay cladding on the inner surface of RPV were introduced. In PASCAL Ver. 4 released in FY 2017, we improved several functions such as the stress intensity factor solutions, probabilistic fracture toughness evaluation models, and confidence level evaluation function by considering epistemic and aleatory uncertainties related to influential parameters. In addition, the probabilistic calculation method was also improved to speed up the failure probability calculations. To strengthen the practical applications of PFM methodology in Japan, PASCAL code has been improved since FY 2018 to enable PFM analyses of RPVs subjected to a broad range of transients corresponding to both PWRs and boiling water reactors, including pressurized thermal shock, low-temperature over pressure, and normal operational transients. In particular, the stress intensi
Tobita, Minoru*; Konda, Miki; Omori, Takeshi*; Nabatame, Tsutomu*; Onizawa, Takashi*; Kurosawa, Katsuaki*; Haraga, Tomoko; Aono, Ryuji; Mitsukai, Akina; Tsuchida, Daiki; et al.
JAEA-Data/Code 2022-007, 40 Pages, 2022/11
JAEA-Data-Code-2022-007.pdf:1.99MB
Radioactive wastes generated from nuclear research facilities in Japan Atomic Energy Agency are planning to be buried in the near surface disposal field. Therefore, it is required to establish the method to evaluate the radioactivity concentrations of radioactive wastes until the beginning of disposal. In order to contribute to this work, we collected and analyzed concrete, ash, ceramic and brick samples generated from JRR-3, JRR4 and JRTF facilities. In this report, we summarized the radioactivity concentrations of 24 radionuclides (H, C, Cl, 
Ca, Co, Ni, Sr, Nb, Tc, Ag, I, Cs, 
Ba, Eu, Eu, 
Ho, U, U, Pu, 
Pu, Pu, Am, 
Am, Cm) which were obtained from radiochemical analysis of the samples in fiscal years 2020-2021.
Takeuchi, Ryuji; Murakami, Hiroaki; Nishio, Kazuhisa*
JAEA-Data/Code 2022-008, 184 Pages, 2023/01
JAEA-Data-Code-2022-008.pdf:8.2MBJAEA-Data-Code-2022-008-appendix1(DVD-ROM).zip:327.79MBJAEA-Data-Code-2022-008-appendix2(DVD-ROM).zip:284.46MB
The Tono Geoscience Center of Japan Atomic Energy Agency (JAEA) has been conducting the groundwater pressure and hydro-chemical monitoring to confirm the restoration process of the surrounding geological environment associated with the backfilling of shafts and tunnels of Mizunami Underground Research Laboratory. This report summarizes the results of the groundwater pressure and hydro-chemical monitoring conducted from FY2020 to FY2021.
Tada, Kenichi; Yamamoto, Akio*; Kunieda, Satoshi; Nagaya, Yasunobu
JAEA-Data/Code 2022-009, 208 Pages, 2023/02
JAEA-Data-Code-2022-009.pdf:3.87MB
The nuclear data processing code has an important role to connect evaluated nuclear data libraries and neutronics calculation codes. Japan Atomic Energy Agency (JAEA) has developed the nuclear data processing code FRENDY since 2013 to generate cross section files from evaluated nuclear data libraries, such as JENDL, ENDF/B, JEFF, and TENDL. The first version of FRENDY was released in 2019. FRENDY version 1 generates ACE files which are used for continuous energy Monte Carlo codes such as PHITS, Serpent, and MCNP. FRENDY version 2 generates multi-group neutron cross-section files from ACE files. The other major improvements are as follows: (1) uncertainty quantification for the probability tables of the unresolved resonance cross-section; (2) perturbation of the ACE file for the uncertainty quantification using a continuous Monte Carlo code; (3) modification of the ENDF-6 formatted nuclear data file. This report describes an overview of the nuclear data processing methods and input instructions for FRENDY.
Takeuchi, Ryuji; Nishio, Kazuhisa*; Hanamuro, Takahiro; Kokubu, Yoko
JAEA-Data/Code 2022-010, 110 Pages, 2023/03
JAEA-Data-Code-2022-010.pdf:6.2MB
The Tono Geoscience Center of Japan Atomic Energy Agency (JAEA) has been conducting the environmental monitoring investigation to confirm the environmental impacts associated with the backfilling of shafts and tunnels at the Mizunami Underground Research Laboratory (MIU). This report summarizes the results of environmental impact investigations conducted as part of the environmental monitoring investigation around the MIU Site from FY2020 to FY2021, which include groundwater level measurement in wells, river flow rate measurement, water analysis of Hazama river, noise and vibration surveys, and soil survey.
Futagawa, Kazuo; Kashimura, Keita; Sato, Daiki*; Kawasaki, Masatsugu
JAEA-Data/Code 2022-011, 75 Pages, 2023/03
JAEA-Data-Code-2022-011.pdf:1.49MB
These statistical results are based on the meteorological data observed at the Nuclear Science Research Institute in Japan Atomic Energy Agency and statistically processed according to "The guideline of meteorological statistics for the safety analysis of nuclear power reactor" (Nuclear Safety Commission on January 28, 1982; revised on March 29, 2001). The statistics are based on 5 years of meteorological data, from January 2017 to December 2021. These are statistical results of wind direction, wind speed, atmospheric stability, etc., which are used for dose assessment of the general public due to radioactive materials discharged into the atmosphere from nuclear reactor facilities.
Shimomura, Kenta; Yamashita, Takuya; Nagae, Yuji
JAEA-Data/Code 2022-012, 270 Pages, 2023/03
JAEA-Data-Code-2022-012.pdf:38.25MB
In a light water reactor, which is a commercial nuclear power plant, a severe accident such as loss of cooling function in the reactor pressure vessel (RPV) and exposure of fuel rods due to a drop in the water level in the reactor can occur when a trouble like loss of all AC power occurs. In the event of such a severe accident, the RPV may be damaged due to in-vessel conditions (temperature, molten materials, etc.) and leakage of radioactive materials from the reactor may occur. Verification and estimation of the process of RPV damage, molten fuel debris spillage and expansion, etc. during accident progression will provide important information for decommissioning work. Possible causes of RPV failure include failure due to loads and restraints applied to the RPV substructure (mechanical failure), failure due to the current eutectic state of low-melting metals and high-melting oxides with the RPV bottom members (failure due to inter-material reactions), and failure near the melting point of the structural members at the RPV bottom. Among the failure factors, mechanical failure is verified by numerical analysis (thermal hydraulics and structural analysis). When conducting such a numerical analysis, the heat transfer properties (thermal conductivity, specific heat, density) and material properties (thermal conductivity, Young's modulus, Poisson's ratio, tensile, creep) of the materials (zirconium, boron carbide, stainless steel, nickel-based alloy, low alloy steel, etc.) constituting the RPV and in-core structures to near the melting point are required to evaluate the creep failure of the RPV. In this document, we compiled data on the properties of base materials up to the melting point of each material constituting the RPV and in-core structures, based on published literature. In addition, because welds exist in the RPV and in-core structures, the data on welds are also included in this report, although they are limited.
Miyakawa, Kazuya; Nakata, Kotaro*
JAEA-Data/Code 2022-013, 19 Pages, 2023/03
JAEA-Data-Code-2022-013.pdf:1.88MB
In the Horonobe Underground Research Laboratory (URL) project, groundwater chemistry was analyzed to investigate changes due to the excavation of the underground facility and to review geochemical models until the fiscal year 2019. From the fiscal year 2020, to proceed remaining important issues deduced from the conclusion of the investigations during the fiscal year 2015-2019, primary data such as groundwater chemistry need to be successively acquired. Here, the chemical analysis of 54 groundwater samples in 2022 from boreholes drilled in the 140 m, 250 m, 350 m gallery in the Horonobe URL, and water rings settled in three vertical shafts is presented. Analytical results include groundwater chemistry such as pH, electrical conductivity, dissolved components (Na
, K, Ca
, Mg, Li, NH
, F
, Cl, Br, NO
, NO
, PO
, SO
, Total-Mn, Total-Fe, Al, B, Sr, Ba, I, alkalinity, dissolved organic carbon, dissolved inorganic carbon, CO, HCO, Fe, sulfide), and 
O, D along with a detailed description of analytical methods.