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A Method of Calculating Critical Size in Multi-Group Neutron Transport Theory for Some Simple Systems

E R Woodcock

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A simple method is developed for obtaining a good approximation to the critical size of some simple nuclear reactors when neutrons of all relevant energies are allowed for by dividing them into a number of energy groups. The method is applicable for any number of energy groups.


PACS

28.20.Gd Neutron transport: diffusion and moderation

28.41.My Reactor control systems

28.41.Ak Theory, design, and computerized simulation

Subjects

Nuclear physics

Dates

Issue 8 (1 August 1953)

Received 17 March 1953



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