Titlebook: Reactor Dosimetry; Volume 1 Volume 2 Do J. P. Genthon,H. R?ttger Conference proceedings 1985 Springer Science+Business Media Dordrecht 1985

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A. Taboada,P. N. Randall,C. Z. Serpan Jr.senting an acceptable risk for collaboration (low, medium, high), the adoption of some measures to deal with credit limits in each client depending on the risk result, penetration on regions with a lower risk, provisioning for high-risk customers, additional safeguards and closer monitoring of their

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Overview: 978-94-010-8873-2978-94-009-5378-9

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Transport Calculation of Neutron Flux and Spectrum in Surveillance Capsules and Pressure Vessel of a The transport code DOT 3.5 was used. Calculations were performed separately for the reactor and the surveillance capsule. Presented are spatial distributions as well as absolute values at most important locations within the capsule and the pressure vessel for BOL and EOL of the first fuel cycle.

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Dosimetry Measurements and Calculation of Fast Neutron Flux in the Reactor Cavity of a 3-Loop Pressu dosimetry material which includes Fe, bare and Cd-shielded Al-Co wires, was installed during a refueling shutdown. The dosimeter arrangement was selected to obtain information on both the axial and azimuthal flux gradients within the reactor cavity.

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