E-LIB Suche - Ergebnisse für: Kyrki-Rajamäki, R.

1

CFD simulation and pattern recognition analysis of the chug..:

Tanskanen, V. ; Jordan, A. ; Puustinen, M..
Annals of Nuclear Energy. 66 (2014) - p. 133-143 , 2014

Link: https://doi.org/10.1016/..

2

Numerical modelling of low-Reynolds number direct contact c..:

Patel, G. ; Tanskanen, V. ; Kyrki-Rajamäki, R.
Annals of Nuclear Energy. 71 (2014) - p. 376-387 , 2014

Link: https://doi.org/10.1016/..

3

TRACE code modeling of the horizontal steam generator of th..:

Vihavainen, J. ; Riikonen, V. ; Kyrki-Rajamäki, R.
Annals of Nuclear Energy. 37 (2010) 11 - p. 1494-1501 , 2010

Link: https://doi.org/10.1016/..

4

An Overview of the Pressurized Thermal Shock Issue inthe Co..:

Lucas, D. ; Bestion, D. ; Bodèle, E....
Science and Technology of Nuclear Installations. 2009 (2008) 1 - p. , 2008

Link: https://doi.org/10.1155/..

5

High performance light water reactor:

Squarer, D. ; Schulenberg, T. ; Struwe, D....
Nuclear Engineering and Design. 221 (2003) 1-3 - p. 167-180 , 2003

Link: https://doi.org/10.1016/..

6

Validation of coupled neutron kinetic/thermal-hydraulic cod..:

Hämäläinen, A. ; Kyrki-Rajamäki, R. ; Mittag, S....
Annals of Nuclear Energy. 29 (2002) 3 - p. 255-269 , 2002

Link: https://doi.org/10.1016/..

7

Validation of coupled neutron kinetic/thermal–hydraulic cod..:

Mittag, S ; Kliem, S ; Weiß, F.P...
Annals of Nuclear Energy. 28 (2001) 9 - p. 857-873 , 2001

Link: https://doi.org/10.1016/..

8

An overview of the pressurized thermal shock issue in the c..:

Lucas, D ; Bestion, D ; Bodéle, E...
Lucas , D , Bestion , D , Bodéle , E , Coste , P , Scheuerer , M , D'Auria , F , Mazzini , D , Smith , B , Tiselj , I , Martin , A , Lakehal , D , Seynhaeve , J M , Kyrki-Rajamäki , R , Ilvonen , M & Macek , J 2009 , ' An overview of the pressurized thermal shock issue in the context of the NURESIM project ' , Science and Technology of Nuclear Installations , vol. 2009 , 583259 . https://doi.org/10.1155/2009/583259. , 2009

Link: https://cris.vtt.fi/en/p..

9

On the simulation of two-phase flow pressurized thermal sho..:

Lucas, D ; Bestion, D ; Bodèle, E...
Lucas , D , Bestion , D , Bodèle , E , Scheuerer , M , D'Auria , F , Mazzini , D , Smith , B , Tiselj , I , Martin , A , Lakehal , D , Seynhave , J-M , Kyrki-Rajamäki , R , Ilvonen , M & Macek , J 2007 , On the simulation of two-phase flow pressurized thermal shock (PTS) . in 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 . Curran Associates Inc. , pp. 358-379 , 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 , Pittsburgh , Pennsylvania , United States , 30/09/07 .. , 2007

Link: https://cris.vtt.fi/en/p..

10

An Overview of the Pressurized Thermal Shock Issue in the C..:

M. Ilvonen ; J. Macek ; D. Lakehal...
http://dx.doi.org/10.1155/2009/583259. , 2009

Link: https://doi.org/10.1155/..

11

Validation of coupled codes for VVERs by analysis of plant ..:

Mittag, R ; Kliem, S ; Weiss, F.P...
Mittag , R , Kliem , S , Weiss , F P , Kyrki-Rajamäki , R , Hämäläinen , A , Langenbuch , S , Danilin , S , Hadek , J , Hegyi , G , Kuchin , A & Panayotov , D 2001 , Validation of coupled codes for VVERs by analysis of plant transients . in Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications : Workshop Proceedings . OECD NEA Nuclear Energy Agency , NEA Committee on the Safety of Nuclear Installations. Report , no. NEA/CSNI/R(2001)2/VOL1 , pp. 309-324 , OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes , Barcelona , Spain , 10/04/00 .. , 2001

Link: https://cris.vtt.fi/en/p..

12

Modeling of realistic pebble bed reactor geometries using t..:

Rintala, Ville ; Suikkanen, Heikki ; Leppänen, Jaakko.
Annals of Nuclear Energy. 77 (2015) - p. 223-230 , 2015

Link: https://doi.org/10.1016/..

13

Discrete element modelling of pebble packing in pebble bed ..:

Suikkanen, Heikki ; Ritvanen, Jouni ; Jalali, Payman.
Nuclear Engineering and Design. 273 (2014) - p. 24-32 , 2014

Link: https://doi.org/10.1016/..

14

PACTEL and PWR PACTEL Test Facilities for Versatile LWR App..:

Kouhia, Virpi ; Purhonen, Heikki ; Riikonen, Vesa...
Science and Technology of Nuclear Installations. 2012 (2012) - p. 1-8 , 2012

Link: https://doi.org/10.1155/..

15

PACTEL integral test facility – Description of versatile ap..:

Purhonen, Heikki ; Puustinen, Markku ; Riikonen, Vesa..
Annals of Nuclear Energy. 33 (2006) 11-12 - p. 994-1009 , 2006

Link: https://doi.org/10.1016/..