STP1228

    Neutron Fluence Determination for WER-440 Reactor Pressure Vessel Ageing Surveillance

    Published: Jan 1994


      Format Pages Price  
    PDF (104K) 7 $25   ADD TO CART
    Complete Source PDF (15M) 7 $131   ADD TO CART


    Abstract

    The neutron flux and fluence determination on Bulgarian WER-440/230 (Units No 1–4 of Kozloduy NPP) Reactor Pressure Vessels is discussed. In these reactors weld 4 of RPV undergoes the most severe irradiation embrittlement. The choice of the neutron transport calculational parameters is substantiated. The inconsistency of 3D neutron flux values obtained by the 3D code TORT and by the synthesis method of DOT 2D results in the point of most severe irradiation embrittlement is within 3% limits range. Radiochemical analysis of the templets sampled out from the Unit No 2 vessel after 16 cycles of exploitation, before and after the annealing, was carried out. The calculated and experimental values of the neutron fluence on the Unit 2 RPV are compared.

    Keywords:

    WER-440, pressure vesse, neutron fluence


    Author Information:

    Ilieva, KD
    Senior research, Institute for Nuclear Research and Nuclear Energy, Sofia,

    Apostolov, TG
    Senior research, Institute for Nuclear Research and Nuclear Energy, Sofia,

    Belousov, SI
    Research fellow, Institute for Nuclear Research and Nuclear Energy, Sofia,

    Antonov, SY
    Research fellow, Institute for Nuclear Research and Nuclear Energy, Sofia,


    Paper ID: STP15095S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP15095S


    CrossRef ASTM International is a member of CrossRef.