Markku Puustinen
Lappeenranta University of Technology
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Featured researches published by Markku Puustinen.
Science and Technology of Nuclear Installations | 2014
Hua Li; Walter Villanueva; Markku Puustinen; Jani Laine; Pavel Kudinov
Steam venting and condensation in a large pool of water creates both a source of heat and a source of momentum. Complex interplay between these two sources leads to either thermal stratification or ...
Science and Technology of Nuclear Installations | 2012
Virpi Kouhia; Heikki Purhonen; Vesa Riikonen; Markku Puustinen; Riitta Kyrki-Rajamäki; Juhani Vihavainen
This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and emergency core cooling systems, was designed to model the thermal-hydraulic behaviour of VVER-440-type reactors. The facility has been utilized in miscellaneous applications and experiments, for example, in the OECD International Standard Problem ISP-33. PACTEL has been upgraded and modified on a case-by-case basis. The latest facility configuration, the PWR PACTEL facility, was constructed for research activities associated with the EPR-type reactor. A significant design basis is to utilize certain parts of PACTEL, and at the same time, to focus on a proper construction of two new loops and vertical steam generators with an extensive instrumentation. The PWR PACTEL benchmark exercise was launched in 2010 with a small break loss-of-coolant accident test as the chosen transient. Both facilities, PACTEL and PWR PACTEL, are maintained fully operational side by side.
Nuclear Engineering and Design | 2002
Markku Puustinen
Abstract This paper deals with the natural circulation flow characteristics of the VVER-440 geometry at reduced coolant inventory. Special emphasis is on the flow rate of the primary circuits during the two-phase flow regime. For studying two-phase natural circulation flow phenomena in a VVER geometry a series of cold leg small break loss-of-coolant accident (SBLOCA) tests was carried out in the PArallel Channel TEst Loop (PACTEL), a 1/305 volumetrically scaled model of a VVER-440 reactor. The tests were conducted with break areas ranging from 0.1 to 1.5 % of the scaled cold leg cross-sectional area of the reference reactor. A partial failure of the high-pressure injection system (HPIS) was assumed. The tests reveal a trend towards an increasing primary circuit mass flow rate with decreasing inventory. This contradicts the findings of earlier tests in multi-loop VVER geometry. With single-loop facilities, increased mass flow rates at reduced inventories have been reported before. The increase of the two-phase flow rate turns out to be a consequence of the combined effect of break size, pressure range and secondary side feed and bleed procedure. The physical phenomena of flow stagnation in the primary circuits, system pressurization, asymmetric loop flows, and loop seal clearing and refilling take place during the natural circulation cooling process from single-phase into two-phase and boiler–condenser modes. In addition, flow reversal in the undermost tubes of the horizontal steam generators (SG) is observed. These phenomena are discussed briefly while a general insight into the course of the tests is presented.
Nuclear Engineering and Design | 2018
Ignacio Gallego-Marcos; Pavel Kudinov; Walter Villanueva; Ralf Kapulla; Sidharth Paranjape; Domenico Paladino; Jani Laine; Markku Puustinen; Antti Räsänen; Lauri Pyy; Eetu Kotro
Spargers are mutli-hole injection pipes used in Boiling Water Reactors (BWR) and Advanced Pressurized (AP) reactors to condense steam in large water pools. A steam injection induces heat, momentum and mass sources that depend on the steam injection conditions and can result in thermal stratification or mixing of the pool. Thermal stratification reduces the steam condensation capacity of the pool, increases the pool surface temperature and thus the containment pressure. Development of models with predictive capabilities requires the understanding of basic phenomena that govern the behavior of the complex multi-scale system. The goals of this work are (i) to analyze and interpret the experiments on steam injection into a pool through spargers performed in the large-scale facilities of PPOOLEX and PANDA, and (ii) to discuss possible modelling approaches for the observed phenomena. A scaling approach was developed to address the most important physical phenomena and regimes relevant to prototypic plant conditions. The focus of the tests was on the low steam mass flux and oscillatory bubble condensation regimes, which are expected during a long-term steam injection transient, e.g. in the case of a Station Black Out (SBO). Exploratory tests were also done for chugging and stable jet conditions. The results showed a similar behavior in PPOOLEX and PANDA in terms of jet induced by steam condensation, pool stratification, and development of hot layer and erosion of the cold one. A correlation using the Richardson number is proposed to model the erosion rate of the cold layer as a function of the pool dimensions and steam injection conditions.
Annals of Nuclear Energy | 2014
V. Tanskanen; A. Jordan; Markku Puustinen; Riitta Kyrki-Rajamäki
Archive | 1998
Jari Tuunanen; Jyrki Kouhia; Heikki Purhonen; Vesa Riikonen; Markku Puustinen
Annals of Nuclear Energy | 2006
Heikki Purhonen; Markku Puustinen; Vesa Riikonen; Riitta Kyrki-Rajamäki; Juhani Vihavainen
Archive | 2013
Jani Laine; Markku Puustinen; Antti Räsänen
Archive | 2009
Jani Laine; Markku Puustinen
Nuclear Engineering and Design | 2015
Walter Villanueva; Hua Li; Markku Puustinen; Pavel Kudinov