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NEUTRON SOURCES FOR USE IN REACTOR STARTUP

A.B. de Saint Maurice

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Abstract

The particular properties of the Westinghouse Testing Reactor are used in the design of the neutron sources to be used both in its startup and in the critical experiments. Specifically the WTR is a high flux irradiation facility using highly enriched U/sup 235/ as fuel and light water as moderator and coolant. The amount of reactivity control is such that the shutdown multiplication is 0.85 under normal operating conditions. The sources considered are the D/sup 2/( gamma ,n)H/sup 1/ reaction, the Be/sup 9/( gamma ,n)Be/sup 8/ reaction Sb-Be coaxial neutron source, Sb-- Be homogeneous neutron source, and Po-- Be mixture neutron source. Discussions are included on the selection of neutron source type, subcritical flux determination, neutron source specification for the WTR critical, neutron flux varintion in the WTR, and neutron source containers. (M.H.R.)

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The particular properties of the Westinghouse Testing Reactor are used in the design of the neutron sources to be used both in its startup and in the critical experiments. Specifically the WTR is a high flux irradiation facility using highly enriched U/sup 235/ as fuel and light water as moderator and coolant. The amount of reactivity control is such that the shutdown multiplication is 0.85 under normal operating conditions. The sources considered are the D/sup 2/( gamma ,n)H/sup 1/ reaction, the Be/sup 9/( gamma ,n)Be/sup 8/ reaction Sb-Be coaxial neutron source, Sb-- Be homogeneous neutron source, and Po-- Be mixture neutron source. Discussions are included on the selection of neutron source type, subcritical flux determination, neutron source specification for the WTR critical, neutron flux varintion in the WTR, and neutron source containers. (M.H.R.)

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Available abstract

The particular properties of the Westinghouse Testing Reactor are used in the design of the neutron sources to be used both in its startup and in the critical experiments. Specifically the WTR is a high flux irradiation facility using highly enriched U/sup 235/ as fuel and light water as moderator and coolant. The amount of reactivity control is such that the shutdown multiplication is 0.85 under normal operating conditions. The sources considered are the D/sup 2/( gamma ,n)H/sup 1/ reaction, the Be/sup 9/( gamma ,n)Be/sup 8/ reaction Sb-Be coaxial neutron source, Sb-- Be homogeneous neutron source, and Po-- Be mixture neutron source. Discussions are included on the selection of neutron source type, subcritical flux determination, neutron source specification for the WTR critical, neutron flux varintion in the WTR, and neutron source containers. (M.H.R.)

Key concepts: Neutron source, Neutron flux, Neutron poison, Neutron, Neutron cross section, Radiochemistry, Neutron moderator, Nuclear engineering

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