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

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

Paper describes the new approach of fitting axial fuel burn-up patterns in peripheral fuel assemblies of VVER-1000 type reactors, on the base of ex-core neutron leakage measurements, neutron-physical calculations and in-core SPND measured data. The developed approach uses results of new ex-vessel me...

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Main Authors: Borodkin Pavel, Borodkin Gennady, Khrennikov Nikolay
Format: Article
Language:English
Published: EDP Sciences 2016-01-01
Series:EPJ Web of Conferences
Online Access:http://dx.doi.org/10.1051/epjconf/201610602008
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spelling doaj-c94dcd826512444c94090a61c6e13b5f2021-08-02T13:43:13ZengEDP SciencesEPJ Web of Conferences2100-014X2016-01-011060200810.1051/epjconf/201610602008epjconf-ISRD2015_02008Methodology 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 CalculationsBorodkin Pavel0Borodkin Gennady1Khrennikov Nikolay2Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS)Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS)Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS)Paper describes the new approach of fitting axial fuel burn-up patterns in peripheral fuel assemblies of VVER-1000 type reactors, on the base of ex-core neutron leakage measurements, neutron-physical calculations and in-core SPND measured data. The developed approach uses results of new ex-vessel measurements on different power units through different reactor cycles and their uncertainties to clear the influence of a fitted fuel burn-up profile to the RPV neutron fluence calculations. The new methodology may be recommended to be included in the routine fluence calculations used in RPV lifetime management and may be taken into account during VVER-1000 core burn-up pattern correction.http://dx.doi.org/10.1051/epjconf/201610602008
collection DOAJ
language English
format Article
sources DOAJ
author Borodkin Pavel
Borodkin Gennady
Khrennikov Nikolay
spellingShingle Borodkin Pavel
Borodkin Gennady
Khrennikov Nikolay
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
EPJ Web of Conferences
author_facet Borodkin Pavel
Borodkin Gennady
Khrennikov Nikolay
author_sort Borodkin Pavel
title 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
title_short 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
title_full 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
title_fullStr 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
title_full_unstemmed 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
title_sort 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
publisher EDP Sciences
series EPJ Web of Conferences
issn 2100-014X
publishDate 2016-01-01
description Paper describes the new approach of fitting axial fuel burn-up patterns in peripheral fuel assemblies of VVER-1000 type reactors, on the base of ex-core neutron leakage measurements, neutron-physical calculations and in-core SPND measured data. The developed approach uses results of new ex-vessel measurements on different power units through different reactor cycles and their uncertainties to clear the influence of a fitted fuel burn-up profile to the RPV neutron fluence calculations. The new methodology may be recommended to be included in the routine fluence calculations used in RPV lifetime management and may be taken into account during VVER-1000 core burn-up pattern correction.
url http://dx.doi.org/10.1051/epjconf/201610602008
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AT borodkingennady methodologyoffuelburnupfittinginvver1000reactorcorebyusingnewexvesselneutrondosimetryandincoremeasurementsanditsapplicationforroutinereactorpressurevesselfluencecalculations
AT khrennikovnikolay methodologyoffuelburnupfittinginvver1000reactorcorebyusingnewexvesselneutrondosimetryandincoremeasurementsanditsapplicationforroutinereactorpressurevesselfluencecalculations
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