Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 20
  • 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

Evaluation of impact with high temperature engineering test reactor using realistic model of stack and reactor building

Ono, Masato; Fujiwara, Yusuke; Matsumoto, Tetsuro*; Iigaki, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 19(2), p.110 - 120, 2020/06

Integrity confirmation for buildings against collisions of projectiles has been conducted to evaluate collisions between a projectile with simple shape and a wall using empirical formulas. It is a matter of fact, there is a possibility that structures with complex shape such as stack may collide with a reactor building. However, there were not so many studies of collisions between structures with complex shape and buildings in the literature. Impact evaluation was carried out using reactor building and stack with real shape and adequate physical property. It was found that ceiling of reactor building was not damaged by the collision, confirming that there was no effect inside of reactor building.

JAEA Reports

On the requirement for remodelling the spent nuclear fuel transportation casks for research reactors; A Review of the drop impact analyses of JRC-80Y-20T

Review Group on the Structure of the Spent Nuclear Fuel Transportation Casks for

JAERI-Review 2005-023, 133 Pages, 2005/07

JAERI-Review-2005-023.pdf:18.88MB

The Japan Atomic Energy Research Institute (JAERI) constructed two stainless steel transportation casks, JRC-80Y-20T, for spent nuclear fuels of research reactors and had utilized them for transportation since 1981. A modification of the design was applied to the USA for transportation of silicide fuels. Additional analyses employing the impact analysis code LS-DYNA that was often used for safety analysis were submitted by the JAERI to the USA to show integrity of the packages; the casks were still not approved, because inelastic deformation was occurred on the surface of the lid touching to the body. To resolve this problem on design approval of transportation casks, a review group was formed at the end of this June. The group examined the impact analyses by reviewing the input data and performing the sensitivity analyses. As the drop impact analyses were found to be practically reasonable, it was concluded that the approval of the USA for the transportation casks could not be obtained just by revising the analyses; therefore, remodelling the casks is required.

Journal Articles

Long-term contaminant migration and impacts from uranium mill tailings

H.Camus*; R.Little*; D.Acton*; A.Agueero*; D.Chambers*; L.Chamney*; J.L.Daroussin*; J.Droppo*; C.Ferry*; E.Gnanapragasam*; et al.

Journal of Environmental Radioactivity, 42, p.289 - 304, 1999/00

 Times Cited Count:16 Percentile:42.11(Environmental Sciences)

no abstracts in English

JAEA Reports

Journal Articles

Computer code system for structural analysis of radioactive materials transport

; *; *

PATRAM 95: 11th Int. Conf. on the Packaging and Transportation of Radioactive Materials, 3, p.1174 - 1181, 1996/00

no abstracts in English

JAEA Reports

Handbook for structural analysis of radioactive material transport casks

JAERI-M 91-060, 164 Pages, 1991/04

JAERI-M-91-060.pdf:3.1MB

no abstracts in English

JAEA Reports

Seismic study on high temperature gas-cooled reactor core

JAERI 1322, 157 Pages, 1991/04

JAERI-1322.pdf:5.34MB

no abstracts in English

Journal Articles

Development of simplified computer codes for impact analysis of radioactive materials transport casks, 1st report; Computer code CRUSH for impact analysis of casks with shock absorbers

; *

Nihon Genshiryoku Gakkai-Shi, 33(4), p.381 - 390, 1991/04

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Benchmark study of some thermal and structural computer codes for nuclear shipping casks

; Nanae, Y.*; Shimada, H.*; Shimada, A.*

Nihon Genshiryoku Gakkai-Shi, 26(9), p.781 - 792, 1984/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

SHOCK-JR; A Computer Program to Analyze Impact Response of Shipping Container

; *; Shimada, A.*; *

JAERI-M 83-010, 48 Pages, 1983/02

JAERI-M-83-010.pdf:1.0MB

no abstracts in English

Journal Articles

Seismic research on block-type HTGR core

; *; *

Nucl.Eng.Des., 71, p.195 - 215, 1982/00

 Times Cited Count:7 Percentile:62.89(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Seismic Test and Analysis of VHTR Core Using One-Stacked Block Column

; *

JAERI-M 9265, 90 Pages, 1981/01

JAERI-M-9265.pdf:3.13MB

no abstracts in English

20 (Records 1-20 displayed on this page)
  • 1