The Phébus FP1 program had a major importance in the development of knowledge on severe accident in the international nuclear safety community and has been helpful for the validation of phenomenological assumptions related to the core melt accident progression and then for the validation of simulation tools. The paper presents the contribution of the Phébus FP program to the calculation of radioactive releases to the atmosphere for reference accident scenarios (named "reference Source Term") in case of a severe accident in a French PWR. The system-level code ASTEC is used for these evaluations. This approach has then been completed by the probabilistic approach (L2 PSA) which includes calculations of radioactive release for a very large num...
This paper introduces the new approach of risk analysis established by the French Ministry of the En...
Under postulated severe accident conditions in a nuclear reactor most of the radioactivity would be ...
This paper deals with a general methodology to evaluate the Source Term (ST) and the Radiological Co...
The Phébus FP1 program had a major importance in the development of knowledge on severe accident in ...
International audienceOne main goal of the severe accident integral code ASTEC V2, jointly developed...
International audienceIn the event of an accident occurring in a nuclear power plant (NPP), being ab...
International audienceThe French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and the G...
For several years the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and the Germa...
The estimation of core inventory and source term of nuclear reactor is a part of procedures for cond...
The estimation of core inventory and source term of nuclear reactor is a part of procedures for cond...
Nowadays, the available radioactive source term analyses in a nuclear power plant are done by so cal...
Modelling the behaviour of fission product (FP) in a nuclear reactor coolant system (RCS) undergoing...
Analyses of severe accidents in nuclear power plants by using integral codes are necessary in order ...
Analyses of severe accidents in nuclear power plants by using integral codes are necessary in order ...
The international Phébus FP (fission product) programme investigated core degradation and radioactiv...
This paper introduces the new approach of risk analysis established by the French Ministry of the En...
Under postulated severe accident conditions in a nuclear reactor most of the radioactivity would be ...
This paper deals with a general methodology to evaluate the Source Term (ST) and the Radiological Co...
The Phébus FP1 program had a major importance in the development of knowledge on severe accident in ...
International audienceOne main goal of the severe accident integral code ASTEC V2, jointly developed...
International audienceIn the event of an accident occurring in a nuclear power plant (NPP), being ab...
International audienceThe French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and the G...
For several years the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and the Germa...
The estimation of core inventory and source term of nuclear reactor is a part of procedures for cond...
The estimation of core inventory and source term of nuclear reactor is a part of procedures for cond...
Nowadays, the available radioactive source term analyses in a nuclear power plant are done by so cal...
Modelling the behaviour of fission product (FP) in a nuclear reactor coolant system (RCS) undergoing...
Analyses of severe accidents in nuclear power plants by using integral codes are necessary in order ...
Analyses of severe accidents in nuclear power plants by using integral codes are necessary in order ...
The international Phébus FP (fission product) programme investigated core degradation and radioactiv...
This paper introduces the new approach of risk analysis established by the French Ministry of the En...
Under postulated severe accident conditions in a nuclear reactor most of the radioactivity would be ...
This paper deals with a general methodology to evaluate the Source Term (ST) and the Radiological Co...