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- Journeau, Christophe, et al.
(författare)
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SAFEST ROADMAP FOR CORIUM EXPERIMENTAL RESEARCH IN EUROPE
- 2016
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Ingår i: PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4. - : ASME Press. - 9780791850046
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Konferensbidrag (refereegranskat)abstract
- SAFEST (Severe Accident Facilities for European Safety Targets) is a European project networking the European corium experimental laboratories with the objective to establish coordination activities, enabling the development of a common vision and research roadmaps for the next years, and of the management structure to achieve these goals. In this frame, a European roadmap on corium experimental research has been written to define research challenges to contribute to further reinforcement of Gen II and III NPP safety. It is based on the research priorities deteimined by SARNET SARP group as well as those from the recently formulated in the NUGENIA Roadmap for severe accidents and the recently published NUGENIA Global Vision report. It also takes into account issues identified in the analysis of the European stress tests and from the interpretation of the Fukushima accident. 19 relevant issues related to corium have been selected during these prioritization efforts. These issues have been compared to a survey of the European corium experimental facilities and corium analysis laboratories. Finally, the coherence between European infrastructures and R&D needs has been assessed and a table linking issues and infrastructures has been derived. It shows a few lacks in EU corium infrastructures, especially in the domains of core late reflooding impact on source term, Reactor Pressure Vessel failure and corium release, Spent Fuel Pool accidents, as well as the need for a large mass (100500 kg) prototypic corium facility.
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- Zabiego, Magali, et al.
(författare)
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The KROTOS KFC and SERENA/KS1 tests : experimental results and MC3D calculations
- 2010
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Ingår i: 7th International Conference on Multiphase Flow ICMF 2010.
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Konferensbidrag (refereegranskat)abstract
- During a hypothetical severe accident in a Pressurized Light Water Reactor, the hot molten material mixture (corium) issuingfrom the degraded reactor core may generate a steam explosion if it comes in contact with water. Such an explosion maydamage the structures and threaten the reactor integrity. The SERENA program is an international OECD project which aims athelping the understanding of the interaction mechanisms between the different components of the system (the hot molten pool,the liquid water, the generated fragments and steam) by providing experimental data and calculation analysis.In the KROTOS facility, energetic steam explosions can be triggered and studied using prototypic corium. CEA takes part in theSERENA program by performing experimental tests in the KROTOS facility designed to allow direct visual observations ofmelt injection into a water tank and mixing conditions (Huhtiniemi 2001). Still in the SERENA frame, pre- and post-testanalysis are also carried out by CEA with the MC3D software. MC3D is developed by IRSN, it is a thermal-hydraulicmultiphase flow code mainly dedicated to ex-vessel and in-vessel Fuel Coolant Interactions (FCI) studies (Meignen 2005).The purpose of this paper is to present the KROTOS experimental setup and instrumentation, expose the experimental resultsand a MC3D analysis of the recent KROTOS tests. The experimental results are presented for the KFC scoping test of theKROTOS program for which the results are not restricted to the SERENA partners. On the contrary, the KROTOS KS1 resultsbeing only available to the SERENA partners, the pre-mixing and explosion MC3D post-KS1 test calculations are proposed butwithout any scale. The calculation hypothesis leading to a good agreement with the experimental results (in terms of jetprogression and void fraction in the system) are discussed.
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- Bechta, Sevostian, et al.
(författare)
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On the EU-Japan roadmap for experimental research on corium behavior
- 2019
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Ingår i: Annals of Nuclear Energy. - : PERGAMON-ELSEVIER SCIENCE LTD. - 0306-4549 .- 1873-2100. ; 124, s. 541-547
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Tidskriftsartikel (refereegranskat)abstract
- A joint research roadmap between Europe and Japan has been developed in severe accident field of light water reactors, focusing particularly on reactor core melt (corium) behavior. The development of this roadmap is one of the main targets of the ongoing EU project SAFEST. This paper presents information about ongoing severe accident studies in the area of corium behavior, rationales and comparison of research priorities identified in different projects and documents, expert ranking of safety issues, and finally the research areas and topics and their priorities suggested for the EU Japan roadmap and future bilateral collaborations. These results provide useful guidelines for (i) assessment of long-term goals and proposals for experimental support needed for proper understanding, interpretation and learning lessons of the Fukushima accident; (ii) analysis of severe accident phenomena; (iii) development of accident prevention and mitigation strategies, and corresponding technical measures; (iv) study of corium samples in European and Japanese laboratories; and (v) preparation of Fukushima site decommissioning.
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- Grishchenko, Dmitry, et al.
(författare)
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Recent progress in the gas-film levitation as a method for thermophysical properties measurements : application to ZrO2-Al2O3system
- 2011
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Ingår i: High Temperatures-High Pressures. - : Old City Publishing. - 0018-1544 .- 1472-3441. ; 40:2, s. 127-149
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Tidskriftsartikel (refereegranskat)abstract
- The gas-film levitation is a technique commonly used for contactless processing and thermophysical properties measurements of oxide and metallic glass-forming melts at elevated temperatures (up to 1650ºC). For the first time, the method has been successfully applied for the levitation of oxide and metallic non-glass forming melts in the temperature range of 1700ºC – 2500ºC. Several subjects are discussed in the paper: (1) the applicability of the gas-film levitation for the sustentation of different materials, (2) methodology of data analysis, (3) uncertainty of thermophysical properties measurements and (4) related theoretical modeling. Finally we provide the results of thermophysical properties measurements of ZrO2 – Al2O3 melts of different compositions within the temperature interval from 1700 to 2350ºC.
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- Meignen, Renaud, et al.
(författare)
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Status of steam explosion understanding and modelling
- 2014
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Ingår i: Annals of Nuclear Energy. - : Elsevier BV. - 0306-4549 .- 1873-2100. ; 74, s. 125-133
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Tidskriftsartikel (refereegranskat)abstract
- The main results of the major international activities related to fuel coolant interactions (FCI) of the last 4-year period are presented and a summary of the knowledge gained regarding understanding and the improvements of modelling is provided. At first, the major outcomes of the OECD SERENA-2 program are presented and discussed. Important clarifications were obtained on the so-called material effect and on FCI code capabilities. We then summarise complementary analytical analyses and experimental programs performed in the frame of the SARNET community. The focus was put on the role of melt fragmentation and solidification, the impact of void on the intensity of an explosion and the triggering mechanisms. As a conclusion, tables summarising the improvements are proposed as well as research priorities.
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