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JAEA Reports

None

Matsumoto, Mitsuo; ;

PNC-TN1410 98-005, 96 Pages, 1998/03

PNC-TN1410-98-005.pdf:2.17MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 97-032, 468 Pages, 1997/08

PNC-TN1410-97-032.pdf:10.35MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 97-014, 87 Pages, 1997/03

PNC-TN1410-97-014.pdf:2.92MB

no abstracts in English

JAEA Reports

None

*; *; *

PNC-TJ1409 97-013, 47 Pages, 1997/03

PNC-TJ1409-97-013.pdf:1.1MB

no abstracts in English

JAEA Reports

None

*; *; *

PNC-TJ1409 97-012, 25 Pages, 1997/03

PNC-TJ1409-97-012.pdf:0.54MB

no abstracts in English

JAEA Reports

None

*; *; *

PNC-TJ1409 97-011, 25 Pages, 1997/03

PNC-TJ1409-97-011.pdf:0.59MB

None

JAEA Reports

None

;

PNC-TN8410 97-066, 304 Pages, 1997/02

PNC-TN8410-97-066.pdf:121.03MB

None

JAEA Reports

None

; ; ; Kato, Masato; ; ;

PNC-TN8410 97-038, 448 Pages, 1997/01

PNC-TN8410-97-038.pdf:200.47MB

None

JAEA Reports

Effects of the chemical decontamination on the component parts of the ATR fuel assembly

; ; ; ; ; ;

PNC-TN9410 96-235, 258 Pages, 1996/03

PNC-TN9410-96-235.pdf:41.18MB

The chemical decontamination technique has been developed in order to remove the crud adhering to the surface of the components constructing the primary coolant system, as a part of the measure to decrease the exposure in the annual inspection. The technique has been already applied to the prototype reactor "Fugen", in the core of which the fuel assemblies were not loaded. The chemical decontamination, for the core in which the fuel assemblies are loaded, has been planned for the purpose of improving the utilization factor. It is necessary to confirm, through the test before putting the plan into practice, that the decontamination reagent does not exert a bad influence upon the components constructing the fuel assembly. This report describes the test results which have been carried out so as to investigate the influence of the reagent on the components constructing the fuel assembly. The outline of the results is as follows: (1)The susceptibility to stress corrosion cracking of the chemical decontamination treatment and the residual decontamination reagent on the components constructing the fuel assembly is low enough. (2)The chemical decontamination treatment and the residual decontamination reagent do not exert a bad influence upon the integrity of the fuel assembly concerning the fuel rod holding function of the spacer and the characteristics of the fretting wear caused on the fuel claddings.

JAEA Reports

None

PNC-TN1010 96-001, 59 Pages, 1996/03

PNC-TN1010-96-001.pdf:2.32MB

no abstracts in English

JAEA Reports

None

PNC-TN1440 94-007, 72 Pages, 1994/09

PNC-TN1440-94-007.pdf:3.48MB

no abstracts in English

JAEA Reports

None

PNC-TN9520 94-004, 23 Pages, 1994/07

PNC-TN9520-94-004.pdf:0.71MB

None

JAEA Reports

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

; ; ; ;

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$$^{2}$$, temperature 280$$^{circ}$$C) 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.

JAEA Reports

None

PNC-TN1440 93-008, 73 Pages, 1993/11

PNC-TN1440-93-008.pdf:3.71MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 92-026, 113 Pages, 1992/01

PNC-TN1410-92-026.pdf:11.01MB

no abstracts in English

JAEA Reports

None

PNC-TN1440 91-022, 74 Pages, 1991/09

PNC-TN1440-91-022.pdf:7.83MB

no abstracts in English

JAEA Reports

None

*

PNC-TN1410 91-049, 18 Pages, 1991/07

PNC-TN1410-91-049.pdf:0.31MB

no abstracts in English

JAEA Reports

None

PNC-TN3410 86-004, 67 Pages, 1986/08

PNC-TN3410-86-004.pdf:2.48MB

None

JAEA Reports

None

*

PNC-TN341 84-15, 18 Pages, 1984/10

PNC-TN341-84-15.pdf:0.83MB

None

JAEA Reports

None

*

PNC-TN352 84-02, 37 Pages, 1984/05

PNC-TN352-84-02.pdf:0.73MB

no abstracts in English

JAEA Reports

None

*; *

PNC-TN844 76-03, 360 Pages, 1976/07

PNC-TN844-76-03.pdf:39.59MB

None

21 (Records 1-20 displayed on this page)