Analysis of tritium distribution and leakage characteristics for two fusion reactor reference designs

From 5th sympostum on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). Results of analyses of the tritium distribution and leakage characteristics for two current fusion power reactor designs -the Princeton Reference Model Tokamak and the LASL/ANL Reference Theta Pinch Reactor--are presented and compared. The philosophy of the model used in these analyses is discussed, and the computer code, developed to carry out the calculations, is described. Consideration is given to the practical aspects of those design features which have the greatest influence on tritium inventories and leakage rates; i.e., (1) the blanket and fuel processing systems, (2) the protective atmospheres, and (3) the application of some special materials as tritium barriers. The results of these analyses have permitted several interesting comparisons to be made between a molten salt-stainless steel reactor design (the Princeton Tokamak model) and a liquid lithiumrefractory metal reactor design (the LASL/ANL Theta-Pinch model). (auth)