Physics Study on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU (DUPIC)

Physics studies have been performed for the compatibility of DUPIC fuel design to the existing CANDU-6. The DUPIC fuel is made of spent pressurized water reactor fuel through a dry process, and the bundle design utilizes an advanced CANDU fuel bundle geometry that is mechanically compatible with the current fuel channel and refueling system. The characteristics of a DUPIC core are compared to the current operation limits and performances of a natural uranium core. The refueling simulations have shown that the channel and bundle powers are well below the operation limits for the two- and four-bundle shift refueling schemes. The fuel performance parameters during the refueling operation reserve enough margin to the stress corrosion cracking threshold of natural uranium fuel. With the aid of burnable poison material in the fuel, the safety performance of a DUPIC core is made comparable to that of a natural uranium core. The details of DUPIC fuel design and analysis are described.