Abstract
The equations of the heat diffusion are solved with the help of a neutron diffusion code. This method is used for the study of two kinds of defects in the fuel plates of the BR2 reactor: cIad bonding defect and uranium inclusion . The corresponding hot spot factors are computed . Defects of circular and rectangular section are studied.
| Original language | English |
|---|---|
| Publisher | SCK CEN |
| Number of pages | 41 |
| State | Published - Dec 1962 |
Publication series
| Name | SCK•CEN Reports |
|---|---|
| Publisher | Studiecentrum voor Kernenergie |
| No. | BLG-188 |
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