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Radiation Protection Dosimetry 2005 115(1-4):100-103; doi:10.1093/rpd/nci038
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© The Author 2005. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Pressure vessel calculations for VVER-440 reactors

G. Hordósy1,*, Gy. Hegyi1, A. Keresztúri1, Cs. Maráczy1, E. Temesvári1, P. Vértes1 and É. Zsolnay2

1 KFKI Atomic Energy Research Institute, 114, P.O. Box 49, H-1525 Budapest, Hungary
2 Institute of Nuclear Technique, 2Budapest University of Technology and Economics, P.O. Box. 91, H-1521 Budapest, Hungary

* Corresponding author: hordosy{at}sunserv.kfki.hu

For the determination of the fast neutron load of the reactor pressure vessel a mixed calculational procedure was developed. The procedure was applied to the Unit II of Paks NPP, Hungary. The neutron source on the outer surfaces of the reactor was determined by a core design code, and the neutron transport calculations outside the core were performed by the Monte Carlo code MCNP. The reaction rate in the activation detectors at surveillance positions and at the cavity were calculated and compared with measurements. In most cases, fairly good agreement was found.


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