Nuclear safety has become a technology following extraordinary industrial investments since the 50’s. Events in the last decades occurring in the Three Mile Island Unit-2, Chernobyl Unit-4 and Fukushima Units 1-3 have challenged the sustainability of nuclear technology and undermined the trust of the public, of the decision makers and even of the scientific community toward nuclear safety. Innovative ideas and proposals are possibly needed to restore the confidence and escape the irreversible loss of competence which also feeds the further degradation of sustainability for the technology. Efforts have been completed by the technological community following each of the disasters and ended-up in reinforcements of the Engineered Safety Feature...
To construct and operate a nuclear research reactor, authorization is required to be obtained by the...
The BEPU (Best Estimate Plus Uncertainty) approach constitutes a valuable and, under some circumstan...
Nuclear thermal hydraulic and accident analysis are based in 3 pillar activities, which consists in:...
The accident analysis performance consists of a fundamental part of the licensing of the Nuclear Po...
The Nuclear Reactor Safety (NRS) has been established since the discovery of nuclear fission, and th...
Abstract. Approaches like Best Estimate Plus Uncertainty (BEPU) and concepts like Safety Margins (SM...
Approaches like Best Estimate Plus Uncertainty (BEPU) and concepts like Safety Margins (SM) are well...
The licensing process of a nuclear power plant is motivated by the need to protect humans and the en...
ALARA (As-Low-As-Reasonably-Achievable) is an early principle in Nuclear Reactor Safety, NRS (Nuclea...
The paper aims at fixing bases for possible strengthening of current Nuclear Reactor Safety (NRS) an...
Abstract: In general, Best Estimate Plus Uncertainty (BEPU) methodology implies application of 'real...
The paper deals with Nuclear Reactor Safety Technology (NRST) involving fission and water cooled or ...
Best estimate codes supplemented by uncertainty evaluation (i.e. BEPU = Best Estimate Plus Uncertai...
THE ELEMENTS FOR THE PROPOSAL ALARA (As-Low-As-Reasonably-Achievable) is an early principle, adopted...
Within the licensing process of the Atucha-2 PHWR (Pressurized Heavy Water Reactor) the BEPU (Best E...
To construct and operate a nuclear research reactor, authorization is required to be obtained by the...
The BEPU (Best Estimate Plus Uncertainty) approach constitutes a valuable and, under some circumstan...
Nuclear thermal hydraulic and accident analysis are based in 3 pillar activities, which consists in:...
The accident analysis performance consists of a fundamental part of the licensing of the Nuclear Po...
The Nuclear Reactor Safety (NRS) has been established since the discovery of nuclear fission, and th...
Abstract. Approaches like Best Estimate Plus Uncertainty (BEPU) and concepts like Safety Margins (SM...
Approaches like Best Estimate Plus Uncertainty (BEPU) and concepts like Safety Margins (SM) are well...
The licensing process of a nuclear power plant is motivated by the need to protect humans and the en...
ALARA (As-Low-As-Reasonably-Achievable) is an early principle in Nuclear Reactor Safety, NRS (Nuclea...
The paper aims at fixing bases for possible strengthening of current Nuclear Reactor Safety (NRS) an...
Abstract: In general, Best Estimate Plus Uncertainty (BEPU) methodology implies application of 'real...
The paper deals with Nuclear Reactor Safety Technology (NRST) involving fission and water cooled or ...
Best estimate codes supplemented by uncertainty evaluation (i.e. BEPU = Best Estimate Plus Uncertai...
THE ELEMENTS FOR THE PROPOSAL ALARA (As-Low-As-Reasonably-Achievable) is an early principle, adopted...
Within the licensing process of the Atucha-2 PHWR (Pressurized Heavy Water Reactor) the BEPU (Best E...
To construct and operate a nuclear research reactor, authorization is required to be obtained by the...
The BEPU (Best Estimate Plus Uncertainty) approach constitutes a valuable and, under some circumstan...
Nuclear thermal hydraulic and accident analysis are based in 3 pillar activities, which consists in:...