[en] Results have been obtained from a simulation of the TRIGA Mark III Berkeley Research Reactor (BRR) using DSNP. The BRR utilizes fuel that is a mixture of zirconium hydride and uranium hydride, with a hydride-to-metal ratio of 1.65 and a ²³⁵U enrichment of 20%. At Berkeley, version 3.4 of DSNP runs on an IBM 3081 Computer. The neutronic modules used to simulate the BRR were CNTRL1, EUTR4, TPOWR4, CORTR4, and FDBEK4. The hydraulic loop consisted of modules LPLEN4, CORTR4, UPLEN4, PIPEUI, IHMXA1, and PIPEIL. As indicated from their names, several of the modules were rewritten to incorporate a better model. The problem-description program was written to allow data entry from the console, and thus the FORTRAN program did not have to be recompiled for differing reactivity insertions. The decay heat module, GAMAR1, was not employed, since the ultimate objective of the simulation was to investigate operation of the reactor beyond its licensed limits. In such cases, decay heat is not a significant contributor to the total power