Basic study of monitoring for vibration, crack generation and propagation

*; *

PNC TJ9602 97-001, 19 Pages, 1997/03

PNC-TJ9602-97-001.pdf:0.73MB

Failure of machine and structure has to be prohibited to avoid the leak of liquid natrium. The technology of detection of pre-existing phenomena before final failure becomes very important. In this basic study, the laser based ultrasonic sensor technique which is one of promising methods was invernstigated to summarize its principle and current status and to know the applicability of this method. Firstly the importance of non-destructive evaluation (NDE) method and the history of laser based NDE were reviewed. The technological basic of the non-contact generation of elastic wave by laser radiation and the non-contact defection of ultrasonic wave by laser interference technique. The difference of two modes of generation of elastic wave, that is, thermal stress mode and ablation mode, was reviewed. The detection methods of ultrasonic wave by laser interference such as homodyne interferometer, time-delay interferometer and confocal Fabry-Perot interferometer were investigated and their principle and characteristics were compared. Finally, examples of application of these methods for rough surface samples and high temperature materials were considered. It was concluded that these laser based NDE techniques were able to be used in practical applications.

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

Aoto, Kazumi; ; ; ; ; Hirakawa, Yasushi

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.

ATR Demonstration reactor integrity verification test for the pressur tube rolled joint portion (Fiscal 1988)

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PNC TN9410 94-052, 251 Pages, 1994/01

PNC-TN9410-94-052.pdf:9.33MB

The structure of the pressure tube rolled joint portion for the ATR Demonstration Reactor is somewhat changed from that for Fugen, in order reduce the residual stress around the portion. Therefore, Constant Temperature Endurance Test and Thermal Cycle Endurance Test have been conducted under the reactor operating conditions except irradiation to examine the rolled joint integrity. (1)Constant Temperature Endurance Test. In fiscal 1988, Constant Temperature Endurance Test have been performed in the Component Test Loop for 2,033 hours under the reactor operating conditions (pressure 75kg/cm, temperature 280C) for the JP-3 specimen (total testing period 4,033 hours) and the JP-4, JP-5 specimens (total testing period 9,533 hours). After the endurance test it was found by the helium leak test that the rolled joint tightness was maintained enough. Therefore, it was confirmed that the reduction of the residual atress at the rolled joint portion which occurred at the initial stage of the operation did not affect the rolled joint tightness. (2)Thermal Cycle Endurance Test. The helium leak test and the ultrasonic flaw detection test were performed before and after Thermal Cycle Endurance Test (the unmber of thermal cycle increaced from 60 times to 140 times in fisical 1988), of which results showed the integrity of the rolled joint tightness and no crack propagation near the rolled joint portion. Therefore, it was confirmed that 140 times thermal cycle which was the design value for the reactor life of 30 years did not affect the rolled joint tightness and the initiation and propagation of a crack even for the specimen with 200 ppm hydrogen.

Development of the ultrasonic testing equipment for FBR; Results of R&D

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PNC TN9420 92-014, 125 Pages, 1992/11

PNC-TN9420-92-014.pdf:9.3MB

This report decribes the development of multi-array type probe for FBR steamgenerator tube. We studied integration between three kinds of probes, which were for axial flaw, for circumferential flaw and for wall thickness flaw, detecting method of accuracy locating probe and basic composition of multi-channel detector. It was comfirmed that each devices had object performance in performance test. We shall use this results to study design and manufacture of ultrasonic testing equipment for steamgenerator of FBR Monju.

None

Nagai, Shuichiro; ; Tobita, Noriyuki; Seki, Masayuki; Tsutagi, Koichi; *;

PNC TN8410 91-010, 49 Pages, 1991/01

PNC-TN8410-91-010.pdf:1.61MB

None

Defect inspection of the JPDR pressure vessel after operation by ultrasonic test

Karyoku Hatsuden, 20(3), 298 Pages, 1969/00

https://ci.nii.ac.jp/naid/40017590463

no abstracts in English