Neutronic shielding analysis of the water-cooled lithium lead test blanketmodule in the ITER machine

During the operations of the next experimental fusion machine three breedin g test blanket modules (TBM) for a power reactor will be inserted in the ho rizontal ports and their performance examined. The insertion will change th e overall shielding capability of the structure and thus the regular operab ility of the machine could be affected. In this paper, I report the Monte C arlo simulations made to account for the water-cooled lithium lead TBM inse rtion in the international thermonuclear experimental reactor (ITER) machin e. A 9 degrees torus sector of ITER is modelled comprising a detailed descr iption of the TBM located in position, with an additional shield in the bac k. Results show that the present project of the WCLL TBM, with an additiona l backshield, is suitable for testing in ITER and does not interfere with t he regular operations of the machine. (C) 2000 Elsevier Science B.V. All ri ghts reserved.