Abstract
The conditions of the vessel ageing (damages through irradiation) that mostly determine the life time of a nuclear reactor depend on the dose received. For the determination of this dose we use two calculation methods: one exact method using the TRIPOLI code that solves the Boltzmann equation with the Monte-Carlo method and one simplified method based on the point-kernel method. The advantages of the second method which is fast (easy reproduction of the results) and deterministic (the effects of difference are possible) compared to the first one which is long and statistical make its development necessary. The qualifications of these methods are done by comparison with the experiment that we reach as following: for the first method, we check the programming of TRIPOLI code (representativity of the collision) and its alignment with SN codes, and we modify the second method in order to use variable linear attenuation coefficients inside each medium to represent better the effects of the spectrum and of the reflection. As part of the checking of the basic physical data and their mode of representation, we present a study of the influence of the energy group averaging of the cross sections and of the number of the
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Citation Formats
Kitsos, S.
Improvement of two calculation methods of the detectors activation and on the PWR 900 MWe vessel. Comparison with the experiment; Amelioration de deux schemas de calcul d`activation de detecteurs et de fluence sur les eprouvettes et la cuve d`un REP 900 MWe. Comparaison avec l`experience.
France: N. p.,
1992.
Web.
Kitsos, S.
Improvement of two calculation methods of the detectors activation and on the PWR 900 MWe vessel. Comparison with the experiment; Amelioration de deux schemas de calcul d`activation de detecteurs et de fluence sur les eprouvettes et la cuve d`un REP 900 MWe. Comparaison avec l`experience.
France.
Kitsos, S.
1992.
"Improvement of two calculation methods of the detectors activation and on the PWR 900 MWe vessel. Comparison with the experiment; Amelioration de deux schemas de calcul d`activation de detecteurs et de fluence sur les eprouvettes et la cuve d`un REP 900 MWe. Comparaison avec l`experience."
France.
@misc{etde_10130721,
title = {Improvement of two calculation methods of the detectors activation and on the PWR 900 MWe vessel. Comparison with the experiment; Amelioration de deux schemas de calcul d`activation de detecteurs et de fluence sur les eprouvettes et la cuve d`un REP 900 MWe. Comparaison avec l`experience}
author = {Kitsos, S}
abstractNote = {The conditions of the vessel ageing (damages through irradiation) that mostly determine the life time of a nuclear reactor depend on the dose received. For the determination of this dose we use two calculation methods: one exact method using the TRIPOLI code that solves the Boltzmann equation with the Monte-Carlo method and one simplified method based on the point-kernel method. The advantages of the second method which is fast (easy reproduction of the results) and deterministic (the effects of difference are possible) compared to the first one which is long and statistical make its development necessary. The qualifications of these methods are done by comparison with the experiment that we reach as following: for the first method, we check the programming of TRIPOLI code (representativity of the collision) and its alignment with SN codes, and we modify the second method in order to use variable linear attenuation coefficients inside each medium to represent better the effects of the spectrum and of the reflection. As part of the checking of the basic physical data and their mode of representation, we present a study of the influence of the energy group averaging of the cross sections and of the number of the groups, as well as study of the influence of the cross sections origin.}
place = {France}
year = {1992}
month = {Nov}
}
title = {Improvement of two calculation methods of the detectors activation and on the PWR 900 MWe vessel. Comparison with the experiment; Amelioration de deux schemas de calcul d`activation de detecteurs et de fluence sur les eprouvettes et la cuve d`un REP 900 MWe. Comparaison avec l`experience}
author = {Kitsos, S}
abstractNote = {The conditions of the vessel ageing (damages through irradiation) that mostly determine the life time of a nuclear reactor depend on the dose received. For the determination of this dose we use two calculation methods: one exact method using the TRIPOLI code that solves the Boltzmann equation with the Monte-Carlo method and one simplified method based on the point-kernel method. The advantages of the second method which is fast (easy reproduction of the results) and deterministic (the effects of difference are possible) compared to the first one which is long and statistical make its development necessary. The qualifications of these methods are done by comparison with the experiment that we reach as following: for the first method, we check the programming of TRIPOLI code (representativity of the collision) and its alignment with SN codes, and we modify the second method in order to use variable linear attenuation coefficients inside each medium to represent better the effects of the spectrum and of the reflection. As part of the checking of the basic physical data and their mode of representation, we present a study of the influence of the energy group averaging of the cross sections and of the number of the groups, as well as study of the influence of the cross sections origin.}
place = {France}
year = {1992}
month = {Nov}
}