Commission (NRC) sponsorship a PWR main steam line break (MSLB) benchmark against coupled system thermal-hydraulic and neutron kinetics codes. The benchmark was very well received internationally. It was felt among the participants that there should be a similar benchmark against the codes for a BWR plant transient. The turbine trip (TT) transients in a BWR are pressurisation events in which the coupling between core phenomena and system dynamics plays an important role. In addition, the data made available from experiments carried out at the plant make the present benchmark very valuable. The NEA and US NRC have approved it for the purpose of validating advanced system best-estimate analysis codes. A small team at Pennsylvania State Univer...
This thesis focuses on the validation of the coupled codes developed in Finland for the safety analy...
Rapid cooling of the reactor pressure vessel at high pressure has a potential of challenging the ves...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
The main purpose of the computational OECD/NEA pressurized water reactor main steam line break (PWR ...
A research activity started at the end of 80’s was substantiated within the context of the participa...
The main purpose of the computational OECD/NEA PWR MSLB-Benchmark is the evaluation of the predictio...
A research activity started at the end of 80’s was substantiated within the context of the participa...
An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the ...
A research activity started at the end of 80’s was substantiated within the context of the participa...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
Incorporating full three-dimensional models of the reactor core into system transient codes allows f...
All of the three exercises of the Organization for Economic Cooperation and Development/Nuclear Regu...
A research activity started at the end of 80’s was substantiated within the context of the participa...
The purpose of this paper is first to discuss the methods developed in our three-dimensional pressur...
A training Workshop /Seminar was organized (F. D’Auria was lead scientist) by Organization for Econo...
This thesis focuses on the validation of the coupled codes developed in Finland for the safety analy...
Rapid cooling of the reactor pressure vessel at high pressure has a potential of challenging the ves...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
The main purpose of the computational OECD/NEA pressurized water reactor main steam line break (PWR ...
A research activity started at the end of 80’s was substantiated within the context of the participa...
The main purpose of the computational OECD/NEA PWR MSLB-Benchmark is the evaluation of the predictio...
A research activity started at the end of 80’s was substantiated within the context of the participa...
An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the ...
A research activity started at the end of 80’s was substantiated within the context of the participa...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
Incorporating full three-dimensional models of the reactor core into system transient codes allows f...
All of the three exercises of the Organization for Economic Cooperation and Development/Nuclear Regu...
A research activity started at the end of 80’s was substantiated within the context of the participa...
The purpose of this paper is first to discuss the methods developed in our three-dimensional pressur...
A training Workshop /Seminar was organized (F. D’Auria was lead scientist) by Organization for Econo...
This thesis focuses on the validation of the coupled codes developed in Finland for the safety analy...
Rapid cooling of the reactor pressure vessel at high pressure has a potential of challenging the ves...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...