WIMSD analysis of the positive coolant void mechanism in the CANDU-3 lattice

The Atomic Energy of Canada Technologies (AECLT) of America is submitting the CANDU 3 reactor system for a Design Certification (CD) with the U.S. NRC. The NRC is presently in the preliminary phase of evaluating this natural uranium fueled, heavy water cooled and moderated reactor system. Brookhaven National Laboratory (BNL) is supplying technical assistance and support, particularly in the analysis of the positive void feedback effect known to be inherent in the CANDU 3 design. The purpose of this paper is to present some results from the WIMSD code that was used to study a representative lattice cell of the CANDU 3 reactor under a voided condition.