Abstract
Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered; shielding of the pressure vessel has been developed, but is not in common use; pre-stressing the pressure vessel has been proposed for preventing PTS failures, but its applicability is not yet demonstrated. The large number of successful annealing treatments performed in WWER 440 type reactors as well as research on the effects of annealing treatments suggest applications for western PWRs. The emergency core cooling systems have been modified in WWER 440-type reactors in connection with other mitigation measures. (authors). 37 refs., 18 figs., 2 tabs.
Torronen, K;
Pelli, R;
Planman, T;
Valo, M
[1]
- Technical Research Centre of Finland, Jyvaeskylae (Finland). Combustion and Thermal Engineering Lab.
Citation Formats
Torronen, K, Pelli, R, Planman, T, and Valo, M.
Irradiation embrittlement mitigation.
NEA: N. p.,
1993.
Web.
Torronen, K, Pelli, R, Planman, T, & Valo, M.
Irradiation embrittlement mitigation.
NEA.
Torronen, K, Pelli, R, Planman, T, and Valo, M.
1993.
"Irradiation embrittlement mitigation."
NEA.
@misc{etde_455775,
title = {Irradiation embrittlement mitigation}
author = {Torronen, K, Pelli, R, Planman, T, and Valo, M}
abstractNote = {Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered; shielding of the pressure vessel has been developed, but is not in common use; pre-stressing the pressure vessel has been proposed for preventing PTS failures, but its applicability is not yet demonstrated. The large number of successful annealing treatments performed in WWER 440 type reactors as well as research on the effects of annealing treatments suggest applications for western PWRs. The emergency core cooling systems have been modified in WWER 440-type reactors in connection with other mitigation measures. (authors). 37 refs., 18 figs., 2 tabs.}
place = {NEA}
year = {1993}
month = {Dec}
}
title = {Irradiation embrittlement mitigation}
author = {Torronen, K, Pelli, R, Planman, T, and Valo, M}
abstractNote = {Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered; shielding of the pressure vessel has been developed, but is not in common use; pre-stressing the pressure vessel has been proposed for preventing PTS failures, but its applicability is not yet demonstrated. The large number of successful annealing treatments performed in WWER 440 type reactors as well as research on the effects of annealing treatments suggest applications for western PWRs. The emergency core cooling systems have been modified in WWER 440-type reactors in connection with other mitigation measures. (authors). 37 refs., 18 figs., 2 tabs.}
place = {NEA}
year = {1993}
month = {Dec}
}