Refine your search:     
Report No.
 - 
Search Results: Records 1-10 displayed on this page of 10
  • 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

JAEA Reports

Development of advanced methodology for defect assessment in FBR power plants (Phase II); 2002 Annual Report

Meshii, Toshiyuki*; Watashi, Katsumi; Doi, Motoo; Hashimoto, Takashi

JNC TY4400 2003-002, 63 Pages, 2003/03

JNC-TY4400-2003-002.pdf:3.95MB

no abstracts in English

JAEA Reports

Fundamental study on long-term stability of rock from the macroscopic point of view

Okubo, Seisuke*

JNC TJ7400 2002-011, 86 Pages, 2003/03

JNC-TJ7400-2002-011.pdf:2.99MB

In the fiscal year of l994 when this project was started, a pneumatic creep testing machine was modified. At the end of the fiscal year of l994, Inada granite was purchased, and the preliminary tests such as P-wave velocity measurement and Schmidt hammer testing were carried out. Through the fiscal year of l995, a specimen of Tage tuff under water-saturated condition had been loaded in uniaxial condition in the pneumatic creep testing machine. In the fiscal year of 1995, the uniaxial compression and tension tests, and the short-term creep test of Inada granite were also carried out in the servo-controlled testing machines to obtain the complete stress-strain curves. A hydraulic creep testing machine which was planned to use in the next year was modified for long-term creep testing. Finally, a constitutive equation of variable compliance type was examined based on the experimental results. In the fiscal year of 1996, creep, compression and tension tests were carried out. Two types of pressure maintenance equipment (hydraulic and pneumatic types) were developed and examined. In the fiscal year of 1997, creep, compression and tension tests etc. were again carried out on the basis of the results heretofore. The experimental results of long-term creep testing of Tage tuff, middle-term creep testing of Inada granite were described. In both creep tests, samples were submerged in water. In the fiscal year of 1998, creep testing of Tage tuff was conducted. Results of relatively short-term (middle-term) creep conducted on a servo-controlled testing machine were also described. Sample rock was Sirahama sandstone that showed a considerably large creep strain in low stress level such as 17 % of the uniaxial compression strength. Results of triaxial compression test and uniaxial tension test including unloading-reloading tests were described. In the fiscal years of 1999, 2000 and 2001, creep testing of Tage tuff was continuously conducted. A multi-cylinder hydraulic creep ...

JAEA Reports

None

Ito, Yoshifumi*; Kume, Kyo*; Otani, Nobuo*

JNC TJ4440 2003-002, 284 Pages, 2003/03

JNC-TJ4440-2003-002.pdf:11.68MB

no abstracts in English

JAEA Reports

None

Kume, Kyo*

JNC TJ4440 2003-001, 224 Pages, 2003/03

JNC-TJ4440-2003-001.pdf:6.9MB

no abstracts in English

JAEA Reports

Achievements of Japanese fuel irradiation experiments in HBWR; 1991$$sim$$93

JAERI-Tech 94-021, 79 Pages, 1994/09

JAERI-Tech-94-021.pdf:2.21MB

no abstracts in English

JAEA Reports

Preparation of computer codes for analyzing sensitivity coefficients of burnup characteristics(II)

*; Sanda, Toshio*; *

PNC TJ9124 94-007, 723 Pages, 1994/03

PNC-TJ9124-94-007-Vol1.pdf:22.78MB
PNC-TJ9124-94-007-Vol2.pdf:13.26MB

To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-section library has beeen made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR cores has been achieved. In the design of large LMFBR cores, however, it is important to accurately estimate not only nuclear characteristics, for example, reaction rate distribution and control rod worth but also burnup characteristics, for example, burnup reactivity loss, breeding ratio and so on. Therefore, it is thought to improve the prediction accuracy for burnup characteristics using many burnup data of "JOYO" effectively. It is thought the best way to adjust cross-sections using sensitivity coefficients of burnup characteristics to utilize burnup data of "JOYO". It is able to know the accuracy quantitatively for burnup characteristics of large LMFBR by analyzing the sensitivity coefficients. Therefore in this work computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared since 1992. In 1992 cross-sections adjustment was done by using the data of "JOYO" and the effect was studied. In this year the adequacy of the codes was studied with a view of applying to design of large LMFBR cores. The results are as follows: (1)The computer codes which could analyze sensitivity coefficients of burnup characteristics taking into consideration plural cycles and refueling were prepared, therefore it came to be able to adjust cross-section using burnup data and to estimate the accuracy for design of large LMFBR cores. The characteristics are not only burnup reactivity loss, breeding ratio but also number density, criticality, reactivity worth, reaction rate ratio, and ....

Oral presentation

Preparation of graft adsorbent for recovery of scandium from hot spring

Seko, Noriaki; Kasai, Noboru; Tamada, Masao; Ichikawa, Eiichi*

no journal, , 

no abstracts in English

Oral presentation

Study for the behavior of tritiated water vapor on the organic materials

Kobayashi, Kazuhiro; Hayashi, Takumi; Nishikawa, Yusuke*; Oya, Yasuhisa*; Yamanishi, Toshihiko; Okuno, Kenji*

no journal, , 

no abstracts in English

10 (Records 1-10 displayed on this page)
  • 1