Refine your search:     
Report No.
 - 
Search Results: Records 1-2 displayed on this page of 2
  • 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

Decreasing in neutron multiplication factor in spent fuel storage facilities by changing fuel assembly position in axial direction

Suyama, Kenya; Murazaki, Minoru; Okuda, Yasuhisa*

Annals of Nuclear Energy, 34(5), p.417 - 423, 2007/05

 Times Cited Count:1 Percentile:11.32(Nuclear Science & Technology)

Long-term spent fuel (SF) storage becomes one of the options in nuclear fuel cycle strategies in Japan. In such facilities, criticality safety should be confirmed. Generally, to reduce the neutron multiplication factor, taking wide spaces between spent fuel assemblies is usually considered. However, from the view point that reducing neutron interaction between regions where contain much fissile materials, we are able to shift the assemblies in axial direction alternatively. In this study, the possibility of reduction of neutron multiplication factor by the alternative axial shift of spent nuclear fuel is presented. Several criticality calculations were conducted in order to evaluate the effect of alternative axial assembly shift (A3S) method, which shift the assembly not to horizontal but to vertical directions. For both PWR and BWR fuels, we have smaller neutron multiplication factors if we adopt A3S method than normal configuration. Concerning the end effect which is important for criticality of spent nuclear fuels, it was confirmed that A3S method reduces the end effect. This study shows that several configurations can be considered to optimize criticality safety design of spent fuel storage facilities to reduce the neutron multiplication factor and the end effect for effective operation of such facilities.

Journal Articles

Preliminary criticality safety evaluation of long-term storage of spent nuclear fuels

Okuno, Hiroshi; Suyama, Kenya; Okuda, Yasuhisa*; Yoshiyama, Hiroshi*; Miyoshi, Yoshinori

Proceedings of 8th International Conference on Nuclear Criticality Safety (ICNC 2007), p.140 - 143, 2007/05

In this research, a preliminary critical safe evaluation of a canister was performed, which stored either (1) four UO$$_{2}$$ fuel assemblies (initial uranium enrichment of 4.1 wt%) or (2) four mixed uranium and plutonium oxide (MOX) fuel assemblies (initial plutonium enrichment of 10 wt%) for pressurized-water reactors (PWRs) in the earth for 1000 years without a crash of a fuel bundle. Ten actinide nuclides were chosen, most of which based on "A Guide Introducing Burnup Credit, Preliminary Version", and their compositions were computed with the SWAT code system. Criticality calculations were carried out with the MVP code adopting the computed composition, and the neutron multiplication factor was calculated to be less than 0.9. Issues for consideration were finally summarized.

2 (Records 1-2 displayed on this page)
  • 1