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AbstractAbstract
[en] The core of IRR-1 reactor consists of two types of MTR fuel elements: standard fuel elements with 23 fuel plates and special fuel elements with 17 fuel plates (to allow for insertion of Cd-In-Ag control blades). Spent fuel elements are currently stored in small apart racks, , in the reactor pool. It is planed to relocate all spent fuel elements in a new spent fuel storage pool (SFSP). he elements will be surrounded by Cd boxes, which form a compact array that must be ept subcritical (keff < 0.9) under all possible conditions. The Monte Carlo code MCNP (1) and the transport/diffusion codes WIMS/EXTERMINATOR (EXT2) were both employed in the analyses of the reactor core and the SFSP. The core calculations, besides determining the keff, include the neutron flux and the power distributions. The purpose of this paper is to describe these analyses and discuss their results
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The Israel Nuclear Societies, Tel Aviv (Israel); 287 p; 20 Dec 1999; p. 37-40; 20. conference of the Nuclear Societies in Israel; Dead Sea (Israel); 20-21 Dec 1999
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