Digital Computers in Nuclear Reactor Design

Publisher Summary This chapter discusses the use of digital computers in nuclear reactor design—including, (1) the basic physical processes occurring in a reactor, (2) the development of mathematical relationships among basic physical parameters associated with these processes and the behavior of actual reacting systems, (3) the development of useful methods for the numerical determination of the behavior of such systems, and (4) the preparation of computer programs making use of these methods. It presents a survey of types of problems solved by nuclear codes, of nuclear codes catalogues, and of developments leading to the establishment of a nuclear codes center at Argonne National Laboratory. The chapter discusses some aspects of the basic problem of determining the neutron density distribution in a nuclear reactor and the methods and computer programs that have been developed to obtain approximate solutions to the basic density distribution problem. It also presents a survey of some programs that have been written for the solution of problems associated with other aspects of reactor design such as heat flow, stress analysis, fluid flow, and economics.

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