Methodology of Fuel Burn Up Fitting in VVER-1000 Reactor Core by Using New Ex-Vessel Neutron Dosimetry and In-Core Measurements and its Application for Routine Reactor Pressure Vessel Fluence Calculations

By Borodkin Pavel  

EPJ Web of Conference, Vol. 106, Iss. issue, 2016-02 ,pp. : 02008-02008

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Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

By Dzhalandinov A.  

EPJ Web of Conference, Vol. 106, Iss. issue, 2016-02 ,pp. : 03011-03011

Edp Sciences

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Three-Dimensional (X,Y,Z) Deterministic Analysis of the PCA-Replica Neutron Shielding Benchmark Experiment using the TORT-3.2 Code and Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry

By Pescarini Massimo  

EPJ Web of Conference, Vol. 106, Iss. issue, 2016-02 ,pp. : 06001-06001

Edp Sciences

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BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) – Generation Methodology and Preliminary Testing of two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry

By Pescarini Massimo  

EPJ Web of Conference, Vol. 106, Iss. issue, 2016-02 ,pp. : 04009-04009

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ACS Algorithm in Discrete Ordinates for Pressure Vessel Dosimetry

By Walters William  

EPJ Web of Conference, Vol. 106, Iss. issue, 2016-02 ,pp. : 03006-03006

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