Abstract
Neutron flux, neutron exposure rate and iron displacement cross-section averaged over the neutron spectrum in a two-loop, 632 MWe PWR were calculated. 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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References
F.B. Mynatt, et. al.: The DOT III Two Dimensional Discrete Ordinates Transport Code, 0RNL–TM–4280, September 1973
DLC-2D, MOO Group neutron cross-section data based on ENDF/B’, ORNL, RSIC Data Library Collection
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M. Ravnik, S. Slavič, FASVER 2 - Description of a FORTRAN program for 2D - two group diffusion calculation of power density in PWR core, IJS report - IJS-DP-1698, May 1979.
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© 1985 ECSC, EEC, EAEC, Brussels and Luxembourg
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Kodeli, A., Najžer, M., Remec, I. (1985). Transport Calculation of Neutron Flux and Spectrum in Surveillance Capsules and Pressure Vessel of a PWR. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-009-5378-9_8
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DOI: https://doi.org/10.1007/978-94-009-5378-9_8
Publisher Name: Springer, Dordrecht
Print ISBN: 978-94-010-8873-2
Online ISBN: 978-94-009-5378-9
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