Refine your search:     
Report No.
 - 
Search Results: Records 1-16 displayed on this page of 16
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Residual stress measurement by the neutron diffractometer in Japan

Minakawa, Nobuaki; Morii, Yukio; Moriai, Atsushi; Kikuchi, Kenji

Material Evaluation by X-Ray and Neutron Diffraction, p.H_19_1 - H_19_5, 2001/05

no abstracts in English

JAEA Reports

None

JNC-TN1400 2000-012, 250 Pages, 2000/11

JNC-TN1400-2000-012.pdf:10.18MB

no abstracts in English

JAEA Reports

None

JNC-TN1400 2000-010, 70 Pages, 2000/10

JNC-TN1400-2000-010.pdf:2.87MB

no abstracts in English

JAEA Reports

Meeting for reporting safety research on FBR and ATR in FY1999 (Meetmg report)

*; *

JNC-TN9200 2000-001, 133 Pages, 2000/02

JNC-TN9200-2000-001.pdf:6.8MB

The 11th Meeting for Reporting Safety Research on FBR and ATR was held at the exhibition hall (TECHNO O-ARAI) in OEC on the 15th of December in 1999. The reports of each subject in FY1996-1998 were presented before discussion at this meeting. The 11 subjects had been selected from the subjects (34 in total) on power reactor in fast breeder reactor, earthquake-proof and probabilistic safety assessment according to the decisions of sub-meetings in Sectional Meeting of Safety Research. This meeting was open to the public, and large attendance outside of JNC was invited for the purpose of getting some advice from related specialists. This report contains presentation papers, questions and answers, list of attendance, etc. Refer to the JNC open report for detailed results of safety research in FY1996-1998.

Journal Articles

Thermal stress ratcheting analysis of time-hardening structure

Hada, Kazuhiko

Nippon Kikai Gakkai Rombunshu, A, 65(636), p.108 - 115, 1999/08

no abstracts in English

Journal Articles

Structural integrity test of helical-type intermediate heat exchanger

Kaji, Yoshiyuki; Ioka, Ikuo; Fukaya, Kiyoshi

Nippon Genshiryoku Gakkai-Shi, 38(10), p.47 - 56, 1996/10

no abstracts in English

Journal Articles

Creep-fatigue deformation on curved tubes of Hastelloy XR under in-plane and out-of-plane bending

Kaji, Yoshiyuki; Kikuchi, Kenji;

Nippon Kikai Gakkai Rombunshu, A, 61(586), p.1145 - 1152, 1995/06

no abstracts in English

Journal Articles

Structural integrity test for heat transfer tube of intermediate heat exchanger

Kaji, Yoshiyuki; Ioka, Ikuo;

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.363 - 368, 1995/00

no abstracts in English

JAEA Reports

Development and revisions of simplified crack analysis code CANIS

Furuhashi, Ichiro*; *

PNC-TN9410 94-201, 301 Pages, 1994/04

PNC-TN9410-94-201.pdf:11.35MB

Development and revisions of simplified crack analysis code CANIS-system were done for fracture mechanics evaluation of FBR structures. CANIS-system is composed of CANIS-G, K and -I. Following revisions were done on CANIS-G that evaluate creep fatigue crack growth history. (1.1)0uter crack of cylinder can be treated, addition to inner crack. (1.2)Axial bending load on cylinder can be treated. (1.3)Displacement controlled load such as thermal stresses can be easily treated. (1.4)Libraly of shape functions for net section stress and libraly of stress intensity factor solutions were expanded to support above subjects. (1.5)Material properties such as elasto-plastic stress-strain relation, creep strain relation, creep rupture time and fatigue failure life of 7 kinds of materials those have been gotten in PNC were added on libralies. (1.6)Backward analysis can be done to estimate past time crack shapes. And now CANIS-K that evaluate fracture mechanics parameters and CANIS-I that evaluate crack initiation probability have been developped. CANIS-K can be used in the following subjects. (2.1)Calculate and print details of fracture mechanics parameters such as stress intensity factor K, J-integral and creep J-integral for given crack shapes, and maximum and minimum values and time histories of those parameters. (2.2)Calculate and print crack growth rates, crack opening area and leak rates. CANIS-I can be used in the following subjects. (3.1)Evaluate time dependant fatigue damage and creep damage. (3.2)Evaluate time dependant crack initiation probability with reference of statistical crack initiation data that caused by fatigue damage or by creep damage. Input data format and subroutine programs of these CANIS-G, -K and -I are commonly, so future expansions and revisions will be done easily and commonly. CANIS is very powerful computational tool in the following regions and can be employed in many practical applications. (4.1)Remaining life predictions of cracked ...

JAEA Reports

None

; Inoue, K.*; Obata, Masamichi*

PNC-TN8410 93-299, 26 Pages, 1993/12

PNC-TN8410-93-299.pdf:0.81MB

None

JAEA Reports

None

PNC-TN8420 93-016, 63 Pages, 1993/10

PNC-TN8420-93-016.pdf:1.41MB

None

Journal Articles

Life prediction of creep fatigue at very high temperatures

Kikuchi, Kenji; Kaji, Yoshiyuki; ; *

Nippon Kikai Gakkai Rombunshu, A, 59(557), p.94 - 99, 1993/01

no abstracts in English

JAEA Reports

None

;

PNC-TN8600 92-005, 23 Pages, 1992/03

PNC-TN8600-92-005.pdf:2.73MB

no abstracts in English

Journal Articles

Study radiation or heat oxidation degradation on cable insulating polymeric materials, 2; Heat oxidation degradation

Yagi, Toshiaki; Morita, Yosuke; Kawakami, Waichiro

EIM-88-136, p.49 - 58, 1988/12

no abstracts in English

Journal Articles

Life prediction study of reactor pressure vessel as essential technical foundation for plant life extension

Nakajima, Hajime; ; Kondo, Tatsuo

Proc.Symp.on Nuclear Power Plant Life Extension, p.81 - 93, 1987/00

no abstracts in English

JAEA Reports

Evaluation of Life Predictive for Light Water Reactor Pressure Vessel and its Relevant Theme for the Material Testing

; Nakajima, Hajime; Kondo, Tatsuo

JAERI-M 84-208, 25 Pages, 1984/11

JAERI-M-84-208.pdf:0.95MB

no abstracts in English

16 (Records 1-16 displayed on this page)
  • 1