18 Papers
107 Citations
J. Vendel is an academic researcher from Institut de radioprotection et de sûreté nucléaire. The author has contributed to research in topics: Thermal hydraulics & Pressurized water reactor. The author has an hindex of 8, co-authored 18 publications.
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Papers
Experimental investigation in the TOSQAN facility of heat and mass transfers in a spray for containment application
TL;DR: In this paper, the interaction of a water spray injection used as a mitigation means in order to reduce the gas pressure and temperature in the containment, to produce gases mixing and washout of fission products is studied.
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OECD International Standard Problem ISP-47 on containment thermal-hydraulics—Conclusions of the TOSQAN part
TL;DR: The main objective of the ISP-47 is to assess the capabilities of LumpedParameter and Computational Fluid Dynamics codes in the area of nuclear containment thermal-hydraulics as mentioned in this paper.
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Experimental and numerical approaches of aerosol removal in spray conditions for containment application
Emmanuel Porcheron,Pascal Lemaitre,Denis Marchand,William Plumecocq,Amandine Nuboer,J. Vendel +5 more
TL;DR: In this paper, a water spray injection is used as a mitigation means in order to washout aerosol fission products in nuclear PWRs. But the authors focus on a specific application of the water spray in the context of nuclear safety code validation.
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Characterization of Soot Particles in the Plumes of Over-Ventilated Diffusion Flames
TL;DR: In this article, the physical and optical parameters of soot particles sampled in the plumes of over-ventilated diffusion flames of acetylene, toluene and polymethyl methacrylate are investigated.
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International standard problem ISP-47 on containment thermal hydraulics - Final report
H. J. Allelein,S. Schwarz,K. Fischer,J. Vendel,J. Malet,Ahmed Bentaib,Etienne Studer,H. Paillere,M. Houkema +8 more
- 01 Jan 2007
TL;DR: The ISP-47 benchmark as discussed by the authors was used for code validation using test data from the separate effects facility TOSQAN (7 m3 volume) and the larger-scale MISTRA facility (100 m 3 volume).
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