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JAEA Reports

Data survey and compilation of material property tables of irradiated stainless steel for evaluation of radiation effects on structural material properties of core internals in pressurized water reactors (Contract research)

Kasahara, Shigeki; Fukuya, Koji*; Fujimoto, Koji*; Fujii, Katsuhiko*; Chimi, Yasuhiro

JAEA-Review 2018-013, 171 Pages, 2019/01

JAEA-Review-2018-013.pdf:6.89MB

For structural integrity assessment of reactor internals of light water reactors, it is important to evaluate and predict the property changes of structural materials, based on existing data obtained from austenitic stainless steel irradiated with neutrons. Compilation of the data into tables is valuable for discussing the representative or the most probable values of the properties applied to the assessment. When the data compilation, the data must be distinguished clearly in consideration of different service conditions of core internals of pressurized water reactors (PWR) and boiling water reactors. Main objective of this work is to provide material property tables of irradiated austenitic stainless steel which will be applicable for assessment of structural integrity of core internals of PWRs. To compile the table, published literature reporting irradiated stainless steel data were surveyed and screened by considering the service conditions of PWRs. In addition to the data, various parameters for the data evaluation, e.g. chemical compositions and pre-treatments of the materials, irradiation and examination conditions, were extracted from the literature, and listed into tables.

JAEA Reports

Data survey and compilation of material property tables of irradiated stainless steel for evaluation of radiation effects on structural material properties of core internals in boiling water reactors (Contract Research)

Kasahara, Shigeki; Fukuya, Koji*; Koshiishi, Masato*; Fujii, Katsuhiko*; Chimi, Yasuhiro

JAEA-Review 2018-012, 180 Pages, 2018/11

JAEA-Review-2018-012.pdf:10.71MB

For structural integrity assessment of reactor internals of light water reactors, it is important to evaluate and predict the property changes of structural materials, based on existing data obtained from austenitic stainless steel irradiated with neutrons. Compilation of the data into tables is valuable for discussing the representative or the most probable values of the properties applied to the assessment. In the process of the data compilation, the data must be distinguished clearly in consideration of different service conditions of core internals of boiling water reactors (BWR) and pressurized water reactors. Main objective of this work is to provide material property tables of irradiated austenitic stainless steel which will be applicable for assessment of structural integrity of core internals of BWRs. To compile the table, published literature reporting irradiated stainless steel data were surveyed and screened by considering the service conditions of BWRs. In addition to the data, various parameters for the data evaluation, e.g. chemical compositions and pre-treatments of the materials, irradiation and examination conditions, were extracted from the literature, and listed into the tables.

JAEA Reports

None

*; *

JNC-TJ8420 2000-010, 171 Pages, 2000/03

JNC-TJ8420-2000-010.pdf:5.34MB

no abstracts in English

JAEA Reports

Investigation on the sodium leak accident of Monju; Research report on the thermocouple well at the inlet of the IHX

Aoto, Kazumi; ; ; ; ;

PNC-TN9410 97-076, 29 Pages, 1996/06

PNC-TN9410-97-076.pdf:27.5MB

This report describes the check of the thermocouple well at the inlet of the intermediate heat exchanger (IHX) of C-loop of the secondary heat tansfer system of the prototype fast breeder reactor Monju, regarding the sodium leak accident of the thermocouple well at the outlet of the IHX of the same loop of the secondary heat transfer system of the same plant Monju. Various tests and inspections were performed to check damages at the part with rapid diameter change of the thermocouple well where stress concentration may occur, and to get the information about the integrity of the welded part between the thermocouple well and the attachment. The thermocouple well, the rapid diameter change part, larger and smaller part, respectively, of the thermocouple well, and welded part between the thermocouple well and the attachments were examined as written below. (1)Accurate measurement of the dimension. (2)Vibration test by tapping the thermocouple well. (3)Non destructive testing at some points. (4)Chemical composition analysis. (5)Microscopic observation of metalogical structure. (6)Detailed observation around the rapid diameter change part. (7)Hardness test. (8)Research on corrosion at the clearance. (9)Structure strength test of the thermocouple well. (10)Bending test of the thermocouple's sheath at high temperature.

JAEA Reports

None

Kato, Masato

PNC-TN8600 94-005, 132 Pages, 1994/08

PNC-TN8600-94-005.pdf:7.95MB

no abstracts in English

JAEA Reports

Architecture & maintenance of radiation resistant materials/equipments data base

; ; ; ;

PNC-TN8410 93-192, 129 Pages, 1993/05

PNC-TN8410-93-192.pdf:3.02MB

There is much data available from irradiation tests on various electrical devices and materials simulating conditions found in nuclear plants. This data is very helpful for selecting the components to be used in unclear plant and for equipment design. A data base has been designed to provide easy acquisition and utilization of the test data. Basic items (target user, scope for collecting data, etc.), qualifications (purpose, function, etc.) and input data sheets have been considered in the design of the data base architecture. A prototype data base system architecture has been designed based on these considerations. After improvement and debugging of the prototype system, irradiation data from tests on semiconductors and polymers were entered into the data base using the data sheets. The data base architecture is designed to be simple so that beginners can easily use it. This system has about 1000 electronic equipments data and about 500 polymers data as of July, 1993. Radiation resistance of electronic equipment is now being evaluated using the data base system. Further improvements and rssolution of problems will be made so the data base system can provide optimum support to the design of equipment used in radiation anvironments.

JAEA Reports

None

; ; ; ; ; ;

PNC-TN8450 92-008, 639 Pages, 1992/06

PNC-TN8450-92-008.pdf:74.81MB

None

JAEA Reports

None

; *; *; ; Aoto, Kazumi;

PNC-TN9450 91-003, 28 Pages, 1991/03

PNC-TN9450-91-003.pdf:0.65MB

None

JAEA Reports

Fundamental Tests of High Temperature Wedable Strain Gago

JAERI-M 8590, 14 Pages, 1979/12

JAERI-M-8590.pdf:0.56MB

no abstracts in English

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