Suche nach „[Nadine] [Kaczmarkiewicz]“ hat 5 Publikationen gefunden

NachhaltigF: Maschinenbau und Mechatronik

Zeitschriftenartikel

Giuseppe Bonfigli, S. Buchholz, F. Schäfer, Nadine Kaczmarkiewicz, C. Schuster, M. Sporn

Safety cases for design-basis accidents in LWRs featuring passive systems Part 2 – Numerical investigations

Nuclear Engineering and Design, vol. 372, no. February

2021

DOI: 10.1016/j.nucengdes.2020.110996

Abstract anzeigen

This paper deals with the improvement and validation of numerical tools for the simulation of design basis accidents in nuclear power plants equipped with passive safety systems. Numerical models are implemented in the framework of the 1-D thermal–hydraulic system code ATHLET developed by GRS. Experimental reference data for the validation were obtained at the INKA test facility, a model of the KERENA reactor, reproducing the passive safety systems nearly at full scale. The validation effort focuses firstly on the accuracy of the models for the single passive components, and secondly on the ability of the numerical simulation to reproduce the interaction of all components of the KERENA design under realistic conditions as reproduced in the INKA test facility. Thermal-hydraulic models are presented and validated for two passive components of the KERENA reactor: the passive pressure pulse transmitter and the pressure-controlled flooding valve. Finally, the full model of the INKA facility, including these and other passive components, is discussed and numerical results for simulations reproducing three different design basis accidents are validated by comparison with the corresponding experimental data.

NachhaltigF: Maschinenbau und Mechatronik

Beitrag (Sammelband oder Tagungsband)

Nadine Kaczmarkiewicz, Giuseppe Bonfigli, S. Leyer, T. Wagner

Performance of the Passive Core Flooding System in the Integral Tests of the Project EASY

49. Jahrestagung Kerntechnik / 49th Annual Meeting on Nuclear Technology (AMNT 2018), Berlin , 29. - 30. Mai 2018

2018

Abstract anzeigen

Among nuclear power generation plants, light water reactors are mainly used at present, and are anticipated to be predominant in the future. To improve the light water reactors the development of the LWRs for the next generation is carried out at various organizations. For example, in the USA the Westinghouse AP-1000 is based on proven technology but with an emphasis on passive safety features. The reactor passive core cooling systems include the core makeup tanks system, passive residual heat removal heat exchanger and in-containment refuelling water storage tank. In Russia has been developed the so-called NPP-2006 project of a VVER-1200 nuclear power plant with a V-392M reactor unit. To provide the safety, protection passive systems which don’t depend upon human errors are widely used in this project. Among these are hydrotanks of the second stage and passive heat removal system. In the presented paper an overview of passive core cooling systems for next generation NPPs is given.

NachhaltigF: Maschinenbau und Mechatronik

Beitrag (Sammelband oder Tagungsband)

S. Buchholz, W. Klein-Hessling, Giuseppe Bonfigli, Nadine Kaczmarkiewicz, N. Neukam, F. Schäfer, T. Wagner

The Code System AC2 for the Simulation of Advanced Reactors within the Frame of the German EASY Project

Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) [September 3-8, 2017; Qujiang Int’l Conference Center, Xi’an, Shaanxi, China]

2017

NachhaltigF: Maschinenbau und Mechatronik

Beitrag (Sammelband oder Tagungsband)

S. Buchholz, A. Schaffrath, Giuseppe Bonfigli, Nadine Kaczmarkiewicz, N. Neukam, F. Schäfer, T. Wagner

Evidence of Design Basis Accidents Mitigation Solely with Passive Safety Systems within the Frame of the German EASY Project

Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) [September 3-8, 2017; Qujiang Int’l Conference Center, Xi’an, Shaanxi, China]

2017

NachhaltigF: Maschinenbau und Mechatronik

Beitrag (Sammelband oder Tagungsband)

Nadine Kaczmarkiewicz, Giuseppe Bonfigli, S. Leyer, T. Wagner

Influence of Two-Phase Reverse Flow in the Passive Core Flooding System: Experiments and Simulations within the Frame of the German EASY Project

Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) [September 3-8, 2017; Qujiang Int’l Conference Center, Xi’an, Shaanxi, China]

2017