Reactor criticality parameter evaluation using the Monte Carlo method

Theoretical and practical aspects of application of the Monte Carlo method in reactor problems are analyzed. The theory of some modern methods for solution of homogeneous criticality equations, enabling to evaluate a priori the systematic error (shift) and statistical accuracy of various algorithms is presented. A series of generic problems is discussed: calculation of neutron life-time, the correct account of neutron leakage when calculating critical assemblies by the Monte Carlo method, application of the method for solution of practical tasks in reactor physics