Computational Benchmark Problems—A Review of Recent Work Within the American Nuclear Society Mathematics and Computation Division

An overview of the recent accomplishments of the Computational Benchmark Problems Committee of the American Nuclear Society Mathematics and Computation Division is presented. Solutions of computational benchmark problems in the following eight areas are presented and discussed: (a) high-temperature gas-cooled reactor neutronics, (b) pressurized water reactor (PWR) thermal hydraulics, (c) PWR neutronics, (d) neutron transport in a cylindrical “black” rod, (e) neutron transport in a boiling water reactor (BWR) rod bundle, (f) BWR transient neutronics with thermal feedback, (g) neutron depletion in a heavy water reactor, and (h) heavy water reactor transient neutronics.It is concluded that these problems and solutions are of considerable value to the nuclear industry because they have been and will continue to be useful in the development, evaluation, and verification of computer codes and numerical-solution methods.