Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions

被引：0

作者：

Ederli, Stefano ^{[1
]}

Drai, Patrick ^{[2
]}

Obada, Dorel ^{[3
]}

Girault, Nathalie ^{[2
]}

Mascari, Fulvio ^{[4
]}

机构：

[1] ENEA - Casaccia, Via Anguillarese 301, Roma,00123, Italy

[2] IRSN - Centre de Cadarache, B.P. 3, Saint-Paul-lez-Durance Cedex,13115, France

[3] IRSN - 31 avenue de la Division Leclerc, Fontenay-aux-Roses,92260, France

[4] ENEA - Bologna, Via Martiri di Monte Sole 4, Bologna, Italy

来源：

Annals of Nuclear Energy | 2024年 / 203卷

关键词：

Boiling water reactors - Codes (symbols) - Coolants - Light water reactors - Loss of coolant accidents - Nuclear fuels - Nuclear power plants - Steam generators;

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共 3 条

[1] Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions
Ederli, Stefano
Drai, Patrick
Obada, Dorel
Girault, Nathalie
Mascari, Fulvio
ANNALS OF NUCLEAR ENERGY, 2024, 203
[2] Pressurized Water Small Modular Reactor (SMR), Design Basis Accident Analysis using the ASTEC code
Di Giuli, M.
Sumini, M.
Bandini, G.
23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014), 2014,
[3] FORMATION AND BEHAVIOR OF BURNABLE GASES DURING DESIGN BASIS AND HYPOTHETICAL ACCIDENTS IN PRESSURIZED WATER-REACTORS
HASSMANN, K
ALSMEYER, H
ATOMKERNENERGIE-KERNTECHNIK, 1985, 47 (02): : 97 - 104

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