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Reactor Dosimetry in the Surveillance Program of Kozloduy NPP Reactor Pressure Vessels

Ilieva, KD
Senior scientist,Institute for Nuclear Research & Nuclear Energy of Bulgarian Academy of Sciences,

Belousov, SI
Senior scientist,Institute for Nuclear Research & Nuclear Energy of Bulgarian Academy of Sciences,

Apostolov, TG
Senior scientist,Institute for Nuclear Research & Nuclear Energy of Bulgarian Academy of Sciences,

Monev, M
Manager,Kozloduy NPP,


Pages: 8    Published: Jan 2001


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Source: STP1398-EB


Abstract

The neutron fluence determination methods and approaches applied for Kozloduy NPP reactors of type VVER-1000, Units 5 and 6, and VVER-440, Units 1 to 4, according to the Reactor Pressure Vessel Surveillance Program, are presented. The verification/validation of calculated neutron fluence is carried out by measured activity of ex-vessel detectors installed in the air cavity behind the vessels on units 1 to 6. A methodology for estimation of the neutron fluence for VVER-1000/320 reactor has been developed and applied to surveillance assemblies' sets 1L and 2L of Unit 5 for an assessment of the vessel current embrittlement and prognosis.


Keywords:
neutron fluence, surveillance, activation detectors, validation

Paper ID: STP13582S
Committee/Subcommittee: E10.01
DOI: 10.1520/STP13582S
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