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JAEA Reports

Hydrochemical investigation at the Mizunami Underground Research Laboratory; Compilation of groundwater chemistry data in the Mizunami group and the Toki granite (fiscal year 2016)

Watanabe, Yusuke; Hayashida, Kazuki; Kato, Toshihiro; Kubota, Mitsuru; Aosai, Daisuke*; Kumamoto, Yoshiharu*; Iwatsuki, Teruki

JAEA-Data/Code 2018-002, 108 Pages, 2018/03

JAEA-Data-Code-2018-002.pdf:6.53MB

Japan Atomic Energy Agency has been investigating groundwater chemistry to understand the effect of excavation and maintenance of underground facilities as part of the Mizunami Underground Research Laboratory (MIU) Project in Mizunami, Gifu, Japan. In this report, we compiled data of groundwater chemistry and microbiology obtained at the MIU in the fiscal year 2016 and 2014 to 2016, respectively. In terms of ensuring traceability of data, basic information (e.g. sampling location, sampling time, sampling method and analytical method) and methodology for quality control are described.

Journal Articles

Development of V2UP (Verification & Validation plus Uncertainty quantification and Prediction) procedure for high cycle thermal fatigue in fast reactor; A Challenge to implementation of quality management

Tanaka, Masaaki

Keisan Kogaku Koenkai Rombunshu (CD-ROM), 22, 4 Pages, 2017/05

In the development of the simulation code and the numerical estimation for high cycle thermal fatigue on a structure caused by thermal striping phenomena in sodium cooled fast reactors, implementation of verification and validation (V&V) process is indispensable. A procedure named V2UP (Verification and Validation plus Uncertainty quantification and Prediction) has been made by referring to the existing guidelines regarding the V&V and the methodologies of the safety assessment. In this paper, a challenging installation of quality management procedures into the V2UP procedure is attempted based on the JSCES Standard for "A Model Procedure for Engineering Simulation".

Journal Articles

Present status of dosimetry for radiation application

Kojima, Takuji

Hoshasen To Sangyo, (89), p.4 - 7, 2001/01

This paper describes the present status of dosimetry as one of the useful technique for the process/quality control in radiation application and radiation research/testing. It introduces (a)activities in dose standardization of International Organization for Standardization(ISO) and International Atomic Energy Agency(IAEA) on publication of standards and organization of workshops, (b)recent efforts for consistency check in dose evaluation of electrons having energies above 4MeV, and (c)development status of dosimeter systems relevant to new requirements in dosimetry. It also comments on importance of planning for succession of high-dose dosimetry technology and education/training of dosimetry workers/researchers.

JAEA Reports

Inspection procedure of MONJU fuel pellet

;

JNC-TN8410 2000-015, 7 Pages, 2000/10

JNC-TN8410-2000-015.pdf:0.09MB

Some falsification has been detected in the results of quality control data relating to the diameter of samples of pellets produced in the BNFL's MOX Demonstration Facility (MDF) on September 1999. This document is the outlines of inspection procedure for the MONJU fuel pellet in plutonium fuel center of JNC.

JAEA Reports

A Study on design methods for overpack welds; Acquisition of basic data to quantify welding quality

*; *; *; *; Sago, Hiromi*; *; *

JNC-TJ8400 2000-049, 175 Pages, 2000/02

JNC-TJ8400-2000-049.pdf:7.54MB

In this study basic data on welds of overpack structures for HLW were acquired and a predictive destruction analysis was performed usig the data acquired, in order to examine the viability of weld design methods. The results are summarized as follows: (1)Investigation of Design and Welding Condition for Welded Joint Models. Three welding methods--EBW, TIG and MAG--were selected, and welding conditions were determined so that the welding quality almost equivalent to that of an actual over-pack was ensured. (2)Fabrication of Welded Joint Models. Three welded joint models, one for each of EBW, TIG and MAG, were fabricated. It was confirmed that these models satisfied the quality requirements for Class I specified in JIS Z3104. (3)Sampling and Machining of Strength Test Specimens. Test specimens were taken from each welded joint model, and models for corrosion tests were delivered to the Japan Nuclear Cycle Development Institute (JNC). (4)Strength Test and Micro/macro Structure observation. Tensile tests were conducted at room temperature and at 150$$^{circ}$$C, and fracture toughness tests at 0$$^{circ}$$C and 150$$^{circ}$$C, in order to obtain stress-strain curves, J-R curves and Vickers hardness. In addition, an observation of micro and macro structures was performed. (5)Evaluation. Using the data on the welds obtained from the tests, a fracture prediction analysis and an evaluation of unstable fracture due to weld flaws were performed on the over-pack design described in the second progress report. The following conclusions were obtained: (a)For the overpack design examined, the effects of welds (material property and residual stress) and fabrication tolerance on fracture loading are negligible. (b)In addition, it was decided that even in a design with reduced wall thickness, welds have an insignificant effect on fracture loading because fracture initiates in the center of the shell of the overpack. (c)The size of flaws leading to unstable fracture is on ...

JAEA Reports

A Study on design methods for over pack welds; Acquisition of basic data to quantify welding quality

*; *; *; *; Sago, Hiromi*; *; *

JNC-TJ8400 2000-048, 30 Pages, 2000/02

JNC-TJ8400-2000-048.pdf:1.64MB

In this study basic data on welds of overpack structures for HLW were acquired and a predictive destruction analysis was performed using the data acquired, in order to examine the viability of weld design methods. The results are summarized as follows: (1)Investigation of Design and Welding Conditions for Welded Joint Models. Three welding methods--EBW, TIG and MAG-were selected, and welding conditions were determined so that the welding quality almost equivalent to that of an actual over-pack was ensured. (2)Fabrication of Welded Joint Models. Three welded joint models, one for each of EBW, TIG and MAG, were fabricated. It was confirmed that these models satisfied the quality requirements for Class I specified in JIS Z3104. (3)Sampling and Machining of Strength Test Specimens. Test specimens were taken from each welded joint model, and models for corrosion tests were delivered to the Japan Nuclear Cycle Development Institute (JNC). (4)Strength Test and Micro/macro Structure observation. Tensile tests were conducted at room temperature and at 150$$^{circ}$$C, and fracture toughness tests at 0$$^{circ}$$C and 150$$^{circ}$$C, in order to obtain stress-strain curves, J-R curves and Vickers hardness. In addition, an observation of micro and macro structures was performed. (5)Evaluation. Using the data on the welds obtained from the tests, a fracture prediction analysis and an evaluation of unstable fracture due to weld flaws were performed on the over-pack design described in the second progress report. The following conclusions were obtained: (a)For the overpack design examined, the effects of welds (material property and residual stress) and fabrication tolerance on fracture loading are negligible. (b)In addition, it was decided that even in a design with reduced wall thickness, welds have an insignificant effect on fracture loading because fracture initiates in the center of the shell of the overpack. (c)The size of flaws leading to unstable fracture is on the ...

JAEA Reports

Study on construction technology for repository

Tanai, Kenji; Iwasa, Kengo; Hasegawa, Hiroshi; Miura, K.*; Okutsu, Kazuo*; Kobayashi, Masaaki*

JNC-TN8400 99-046, 177 Pages, 1999/11

JNC-TN8400-99-046.pdf:6.03MB

For the construction of underground facilities comprising access tunnels, connecting tunnels, main tunnels and disposal tunnels, a large number of tunnels will be excavated in deep rock formations. These excavations will extend hundreds kilometers in total length. Therefore, special attention must be paid, to transporting large volume of debris, ventilation, emergency escape routes in case of accident, and other factors. In addition, special attention must also paid to potential accidents which might in underground excavations, including unstable facing phenomena (such as collapse and swelling of facing at weak layer sections), spring water flow resulting collapse of rock, gas eruption, and rock burst. While considering these factors to be emphasized during the construction of geological disposal facilities, the investigation reviewed the existing working methods on individual construction technologies of access tunnels, main tunnels, connecting tunnels, disposal tunnels, and disposal pit, based on the recognition that the present state deals with a wide range of geological environments, and conducted investigation about the construction methods for each tunnel on the basis current technologies, and described the outline of these methods. Furthermore, for the items to be particulaly emphasized on site characterization koko and siting data such as ground pressure and spring water, the investigation reviewed the current countermeasure works, and made survey on the phenomena appeared during actual tunnel construction works and their countermeasres, and carried out a study on effectiveness of these countermeasures. This constructing of disposal site in deep geological formations is basically possible by applying, or confirming, current excavation technologies for tunnels and underground facilities, A systematic construction system combines separate technologies relating to construction, (excavation technology, tunnel support work method, etc.). Such systems ...

JAEA Reports

None

PNC-TJ1211 98-005, 146 Pages, 1998/02

PNC-TJ1211-98-005.pdf:2.42MB

None

JAEA Reports

None

*; *; *; *

PNC-TJ1211 98-004, 68 Pages, 1998/02

PNC-TJ1211-98-004.pdf:4.66MB

None

JAEA Reports

None

; ; Komatsuzaki, Kenji; Momose, Takumaro; Shinohara, Kunihiko

PNC-TN8410 97-002, 42 Pages, 1996/12

PNC-TN8410-97-002.pdf:2.41MB

None

Journal Articles

Radioisotope Production Centre, BATAN, Indonesia

*

Isotope News, 0(508), p.12 - 15, 1996/09

no abstracts in English

JAEA Reports

None

PNC-TJ8164 96-010, 213 Pages, 1996/03

PNC-TJ8164-96-010.pdf:7.67MB

no abstracts in English

JAEA Reports

None

Mukai, Satoru*; Kitao, Hideo*; Tachikawa, Hirokazu*; Fusaeda, Shigeki*; Yanagisawa, Ichiro*; *; *

PNC-TJ1216 96-003, 106 Pages, 1996/03

PNC-TJ1216-96-003.pdf:2.44MB

None

JAEA Reports

None

PNC-TJ1216 96-002, 387 Pages, 1996/03

PNC-TJ1216-96-002.pdf:8.02MB

None

JAEA Reports

None

; Myochin, Munetaka; *; ; *; *;

PNC-TN8440 96-011, 234 Pages, 1996/01

PNC-TN8440-96-011.pdf:29.23MB

None

JAEA Reports

None

; ; Okada, Takashi; Harada, Hideo; Nakamura, Shoji; ;

PNC-TN8440 95-014, 192 Pages, 1995/03

PNC-TN8440-95-014.pdf:7.67MB

None

JAEA Reports

None

Chijimatsu, Masakazu*; Oanh, T.*; Amemiya, Kiyoshi*

PNC-TJ1412 95-002, 186 Pages, 1995/03

PNC-TJ1412-95-002.pdf:9.67MB

None

JAEA Reports

None

Chijimatsu, Masakazu*; Oanh, T.*; Amemiya, Kiyoshi*

PNC-TJ1412 95-001, 106 Pages, 1995/03

PNC-TJ1412-95-001.pdf:4.41MB

None

JAEA Reports

None

Ishikawa, Hirohisa; ; ;

PNC-TN8440 94-020, 70 Pages, 1994/06

PNC-TN8440-94-020.pdf:2.44MB

None

Journal Articles

Present status of dosimetry standardization for radiation processing

Tanaka, Ryuichi

Hoshasen To Sangyo, (59), p.14 - 19, 1993/09

no abstracts in English

29 (Records 1-20 displayed on this page)