Safety cases for design-basis accidents in LWRs featuring passive systems

Author(s):  
Thomas Mull ◽  
Thomas Wagner ◽  
Giuseppe Bonfigli ◽  
Sebastian Buchholz ◽  
Frank Schäfer ◽  
...  
2021 ◽  
Vol 372 ◽  
pp. 110996
Author(s):  
Giuseppe Bonfigli ◽  
Sebastian Buchholz ◽  
Frank Schäfer ◽  
Nadine Kaczmarkiewicz ◽  
Christoph Schuster ◽  
...  

Author(s):  
V. M. Berkovich ◽  
A. B. Malyshev ◽  
G. S. Taranov ◽  
A. K. Podshybyakin ◽  
A. M. Shumsky

A method for provision of containment integrity and localizing capability of the new generation NPPs with WWER reactor units under the beyond design accidents is discussed. The aim is achieved by equipment of NPPs by additional passive systems.


2005 ◽  
Vol 63 (10) ◽  
pp. 863-869 ◽  
Author(s):  
Ye. N. Belov ◽  
Ye. M. Zarichnyak ◽  
V. I. Lutsenko ◽  
I. V. Lutsenko ◽  
V. G. Yakovlev

2020 ◽  
Vol 53 (2) ◽  
pp. 7458-7465
Author(s):  
Shantanu Singh ◽  
George Weiss ◽  
Marius Tucsnak

2021 ◽  
Vol 11 (1) ◽  
pp. 376
Author(s):  
Giacomo Cillari ◽  
Fabio Fantozzi ◽  
Alessandro Franco

Passive solar system design is an essential asset in a zero-energy building perspective to reduce heating, cooling, lighting, and ventilation loads. The integration of passive systems in building leads to a reduction of plant operation with considerable environmental benefits. The design can be related to intrinsic and extrinsic factors that influence the final performance in a synergistic way. The aim of this paper is to provide a comprehensive view of the elements that influence passive solar systems by means of an analysis of the theoretical background and the synergistic design of various solutions available. The paper quantifies the potential impact of influencing factors on the final performance and then investigates a case study of an existing public building, analyzing the effects of the integration of different passive systems through energy simulations. General investigation has highlighted that latitude and orientation impact energy saving on average by 3–13 and 6–11 percentage points, respectively. The case study showed that almost 20% of the building energy demand can be saved by means of passive solar systems. A higher contribution is given by mixing direct and indirect solutions, as half of the heating and around 25% of the cooling energy demand can be cut off.


2020 ◽  
Vol 1574 ◽  
pp. 012157
Author(s):  
Yingcheng Xu ◽  
Wei Feng ◽  
Fei Pei ◽  
Haiyan Wang

Author(s):  
Roberta Ferri ◽  
Andrea Achilli ◽  
Cinzia Congiu ◽  
Gustavo Cattadori ◽  
Fosco Bianchi ◽  
...  

The SPES3 facility is being built at the SIET laboratories, in the frame of an R&D program on Nuclear Fission, led by ENEA and funded by the Italian Ministry of Economic Development. The facility is based on the IRIS reactor design, an advanced medium size, integral layout, pressurized water reactor, based on the proven technology of PWR with an innovative configuration and safety features suitable to cope with Loss of Coolant Accidents through a dynamic coupling of the primary and containment systems. SPES3 is suitable to test the plant response to postulated Design and Beyond Design Basis Events, providing experimental data for code validation and plant safety analysis. It reproduces the primary, secondary and containment systems of the reactor with 1:100 volume scale, full elevation, prototypical fluid and thermal-hydraulic conditions. A design-calculation feedback process, based on the comparison between IRIS and SPES3 simulations, performed respectively by FER, with GOTHIC and RELAP5 coupled codes, and by SIET, with RELAP5 code, led to reduce the differences in the two plants behaviour, versus a 2-inch equivalent DVI line DEG break, considered the most challenging LOCA for the IRIS plant. Once available the final design of SPES3, further calculations were performed to investigate Beyond Design Basis Events, where the intervention of the Passive Containment Condenser is fundamental for the accident recovery. Sensitivity analyses showed the importance of the PCC actuation time, to limit the containment pressure, to reach an early pressure equalization between the primary and containment systems and to allow passive water transfer from the containment to the RPV, enhanced by the ADS Stage-II opening.


2012 ◽  
Vol 2012 ◽  
pp. 1-7 ◽  
Author(s):  
Pavan K. Sharma ◽  
B. Gera ◽  
R. K. Singh ◽  
K. K. Vaze

In water-cooled nuclear power reactors, significant quantities of steam and hydrogen could be produced within the primary containment following the postulated design basis accidents (DBA) or beyond design basis accidents (BDBA). For accurate calculation of the temperature/pressure rise and hydrogen transport calculation in nuclear reactor containment due to such scenarios, wall condensation heat transfer coefficient (HTC) is used. In the present work, the adaptation of a commercial CFD code with the implementation of models for steam condensation on wall surfaces in presence of noncondensable gases is explained. Steam condensation has been modeled using the empirical average HTC, which was originally developed to be used for “lumped-parameter” (volume-averaged) modeling of steam condensation in the presence of noncondensable gases. The present paper suggests a generalized HTC based on curve fitting of most of the reported semiempirical condensation models, which are valid for specific wall conditions. The present methodology has been validated against limited reported experimental data from the COPAIN experimental facility. This is the first step towards the CFD-based generalized analysis procedure for condensation modeling applicable for containment wall surfaces that is being evolved further for specific wall surfaces within the multicompartment containment atmosphere.


2011 ◽  
Vol 173 (2) ◽  
pp. 153-161 ◽  
Author(s):  
Luciano Burgazzi

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