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THE PHYSICS OF A MEDIUM FLUX RESEARCH REACTOR

K. Firth, M. Kerridge, R.F. Mathams, A.J. Salmon, K.G. Stephens, A.J. Trott, Jeffrey Young

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Abstract

The physics problems arising in the design of a research reactor, capable of operating at a peak thermal neutron flux of near 10/sup 14/ neutrons/ cm/sup 2//sec, are described and discussed. The reactor core calculations, when the core is reflected by either water or beryllia, are considered and results obtained using sub-critical facilities are given. These include temperature coefficients, void coefficients, the effects of voids outside the core, the critical masses for various core configurations and the effects of the plate-type control elements. The designs of the radiation shielding and thermal columns are described, the data and methods used are discussed. Calculations concerning the safety aspects of the reactor are described and discussed, the neutron sources and special instruments developed for this sion product detector and a very sensitive gamma -radiation detector. (auth)

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What this paper is about

The physics problems arising in the design of a research reactor, capable of operating at a peak thermal neutron flux of near 10/sup 14/ neutrons/ cm/sup 2//sec, are described and discussed. The reactor core calculations, when the core is reflected by either water or beryllia, are considered and results obtained using sub-critical facilities are given. These include temperature coefficients, void coefficients, the effects of voids outside the core, the critical masses for various core configurations and the effects of the plate-type control elements. The designs of the radiation shielding and thermal columns are described, the data and methods used are discussed. Calculations concerning the safety aspects of the reactor are described and discussed, the neutron sources and special instruments developed for this sion product detector and a very sensitive gamma -radiation detector. (auth)

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Available abstract

The physics problems arising in the design of a research reactor, capable of operating at a peak thermal neutron flux of near 10/sup 14/ neutrons/ cm/sup 2//sec, are described and discussed. The reactor core calculations, when the core is reflected by either water or beryllia, are considered and results obtained using sub-critical facilities are given. These include temperature coefficients, void coefficients, the effects of voids outside the core, the critical masses for various core configurations and the effects of the plate-type control elements. The designs of the radiation shielding and thermal columns are described, the data and methods used are discussed. Calculations concerning the safety aspects of the reactor are described and discussed, the neutron sources and special instruments developed for this sion product detector and a very sensitive gamma -radiation detector. (auth)

Key concepts: Nuclear engineering, Research reactor, Neutron flux, Neutron, Nuclear reactor core, Electromagnetic shielding, Nuclear physics, Neutron temperature

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