Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Simon Schollenberger"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
Investigations of the thermal-hydraulic behavior of pressurized water reactors under accident conditions have been carried out in the PKL test facility at AREVA NP in Erlangen, Germany for many years. The PKL facility models the entire primary side a
Externí odkaz:
https://doaj.org/article/bf2c54710c384d51b899913b83de4755
Autor:
Oliver Herbst, Simon Schollenberger, Klaus Umminger, Holger Schmidt, Ingo Ganzmann, Lars Dennhardt
Publikováno v:
Nuclear Engineering and Design. 336:163-170
AREVA operates a world-wide unique thermal hydraulic platform to ensure high safety standards in the nuclear industry. This platform is operated as an accredited test and inspection body according to ISO 17025 and 17020 to grant high and independentl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6820b52576ecfbf61cdca373a568f059
https://doi.org/10.1016/j.nucengdes.2018.05.014
https://doi.org/10.1016/j.nucengdes.2018.05.014
Publikováno v:
Energy. 211:118612
PKL is a worldwide unique integral test facility for simulation of thermal-hydraulic phenomena, which can occur in Pressurized Water Reactor under abnormal or accident conditions. The test rig replicates the entire primary side and the relevant parts
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1100c65ad1bd66e79a2a6936680f429e
https://doi.org/10.1016/j.energy.2020.118612
https://doi.org/10.1016/j.energy.2020.118612
Publikováno v:
E3S Web of Conferences, Vol 137, p 01016 (2019)
PKL is the only test facility in Europe that replicates the entire primary side and the most important parts of the secondary side of western-type Pressurized Water Reactors (PWR) in the scale of 1:1 in heights. It is also worldwide the only test fac
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6f10981d183e60cfe623de9bcb78ce5e
https://doi.org/10.1051/e3sconf/201913701016
https://doi.org/10.1051/e3sconf/201913701016
Publikováno v:
Chemie Ingenieur Technik. 76:1072-1077
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3a6ff94806953aeebc4c49a0ba3dd4c7
https://doi.org/10.1002/cite.200400079
https://doi.org/10.1002/cite.200400079
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
Investigations of the thermal-hydraulic behavior of pressurized water reactors under accident conditions have been carried out in the PKL test facility at AREVA NP in Erlangen, Germany for many years. The PKL facility models the entire primary side a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a6444744387ecb1bef596e491ba6a869
https://doaj.org/article/bf2c54710c384d51b899913b83de4755
https://doaj.org/article/bf2c54710c384d51b899913b83de4755
PKL Tests on Heterogeneous Inherent Boron Dilution Following SB-LOCA: Applicability to Reactor Scale
Autor:
Simon Schollenberger, Klaus Umminger, Philippe Freydier, Delphine Quintin, Claire Agnoux, Se´bastien Cornille
Publikováno v:
18th International Conference on Nuclear Engineering: Volume 4, Parts A and B.
In the course of a small break LOCA in a Pressurized Water Reactor (PWR) the flow regime in the Reactor Cooling System (RCS) passes through a number of different phases and the filling level may decrease down to the point where the decay heat is tran
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e8af6355d3533c823e2edf0c11f16716
https://doi.org/10.1115/icone18-29400
https://doi.org/10.1115/icone18-29400