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Aoto, Kazumi; ; ; ; ; Hirakawa, Yasushi
PNC TN9450 97-016, 860 Pages, 1997/06
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 transfer 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.
Aoto, Kazumi; ; ; ; ; Hirakawa, Yasushi
PNC TN9420 97-007, 786 Pages, 1997/06
PNC-TN9420-97-007.pdf:311.86MB
The results of the research on the damaged thermocouple well which caused the sodium leak accident at the outlet of the C-loop intermidiate heat exchanger (IHX) of the secondary heat transfer system of the prototype fast breeder reactor Monju are described in this report. A lot of tests, inspections, observations and measurements were carried out to confirm that the thermocouple well and its attachments to the pipe including welded part are normal by checking the possibility of weld failure or corrosion at the clearance which may cause the damage of the thermocouple well, and to get information of the dimensions relating the estimation of the leaked sodium volume and the leakage path, etc. These tests, etc., were performed for the thermocouple well except the fractured surface, the thermocouple well, the welded parts between the thermocouple well and the attachment, and between the attachment and the outlet pipe, etc., as written below. (1)Accurate measurement of the dimension. (2)Inspection to check the fixing condition between the thermocouple well and the attachment. (3)Measurement of the residual stress. (4)Non destructive testing at some points. (5)Chemical composition analysis. (6)Microscopic observation of metalogical structure at the welded 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.
Aoto, Kazumi; ; ; ; ; Hirakawa, Yasushi
PNC TN9410 97-076, 29 Pages, 1996/06
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.
Kimura, Hidetaka; *; *; Kawasaki, Hirotsugu; Aoto, Kazumi;
PNC TN9450 91-003, 28 Pages, 1991/03
None
*
PNC TN9410 90-094, 80 Pages, 1990/06
It is needed for FBR design to know physical properties of the structural materials that will be used for FBR-reactor vessels, -steam generators, and -pipes. In this report, six types of steels that are noted as the structural materials for next steps of FBR are taken up. The six types of steels are as follows ; [SUS 304] [SUS 316 (conventional)] [FBR grade SUS316] [SUS321] [2.25Cr-1Mo steel] [Mod.9Cr-1Mo steel (ASTM A387-91).] Physical properties of the steels are measured on rolled plates made by mills. The measured physical properties are as follows ; [Specific gravity] [Specific heat] [Thermal conductivity] [Thermal expansion] [Young's modulus] [Poisson's ratio.] And also the same kinds of physical properties of S.R. (Stess Relieving) heat treated 2.25Cr-1Mo and Mod.9Cr-1Mo steel plates are measured. Measurement of the physical properties of forgings, pipes, and weld metals of selected types of steels of them will be also carried out in 1990 and all summarized data that will contain the results of this report will be used to determin the criteria design values of the physical properties for the next steps of FBR. (Caution) This report only shows the measurement results of the physical properties of the rolled steel plates but doesn't give the design standards of the physical properties for the next steps of FBR.