EPJ Web of Conferences
Volume 106, 2016ISRD 15 – International Symposium on Reactor Dosimetry
|Number of page(s)||8|
|Section||Transport Calculations (Neutron and Gamma-Ray) and Modeling|
|Published online||03 February 2016|
Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results
1 OKB “GIDROPRESS”, 142103, Ordzhonikidze street, 21, Podolsk, Russia
2 National Research Centre « Kurchatov Institute », 123182, Kurchatov Sq., 1, Moscow, Russia
3 Keldysh Institute of Applied Mathematics, 125047, Miusskaya Sq., 4, Moscow, Russia
Published online: 3 February 2016
Usually the synthesis of two-dimensional and one-dimensional discrete ordinate calculations is used to evaluate neutron fluence on VVER-1000 reactor pressure vessel (RPV) for prognosis of radiation embrittlement. But there are some cases when this approach is not applicable. For example the latest projects of VVER-1000 have upgraded surveillance program. Containers with surveillance specimens are located on the inner surface of RPV with fast neutron flux maximum. Therefore, the synthesis approach is not suitable enough for calculation of local disturbance of neutron field in RPV inner surface behind the surveillance specimens because of their complicated and heterogeneous structure. In some cases the VVER-1000 core loading consists of fuel assemblies with different fuel height and the applicability of synthesis approach is also ambiguous for these fuel cycles. Also, the synthesis approach is not enough correct for the neutron fluence estimation at the RPV area above core top. Because of these reasons only the 3D neutron transport codes seem to be satisfactory for calculation of neutron fluence on the VVER-1000 RPV. The direct 3D calculations are also recommended by modern regulations.
© Owned by the authors, published by EDP Sciences, 2016
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