Zobrazeno 1 - 10
of 126
pro vyhledávání: '"ROCOM"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 11, Pp 4359-4372 (2022)
Turbulent mixing in buoyant flows is an essential mechanism involved in many scenarios related to nuclear safety in nuclear power plants. Comprehensive understanding and accurate predictions of turbulent buoyant flows in the reactor are of crucial im
Externí odkaz:
https://doaj.org/article/48588cdf61b54cc5896cd7b21b61d246
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 9, Pp 3567-3579 (2022)
This paper provides an assessment of fluid transport and mixing processes inside the primary circuit of the test facility ROCOM through the numerical simulation of Test 2.1 with the system code ATHLET. The experiment represents an asymmetric injectio
Externí odkaz:
https://doaj.org/article/863f62692f5446118853515ce4614f15
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3182-3195 (2021)
The implementation and validation of multi-dimensional (multi-D) features in thermal-hydraulic system codes aims to extend the application of these codes towards multi-scale simulations. The main goal is the simulation of large-scale three-dimensiona
Externí odkaz:
https://doaj.org/article/965be03fca6d487ebd6a6e1ac3e029fd
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 12, Pp 2803-2811 (2020)
With the aging of nuclear reactors, embrittlement of the reactor pressure vessel (RPV) steel, as a consequence of routine operations, is highly probable. To ensure operational integrity and safety, prediction and mitigation of compromising damage, br
Externí odkaz:
https://doaj.org/article/e1af102cfbec47eea2822427c5466e35
Autor:
Thomas Höhne, Sören Kliem
Publikováno v:
Fluids, Vol 8, Iss 1, p 4 (2022)
The development, verification, and validation of Computational Fluid Dynamics (CFD) codes in reference to nuclear power plant (NPP) safety has been a focus of many research organizations over the last few decades. Therefore, a collection of Rossendor
Externí odkaz:
https://doaj.org/article/142ab6ca4eb5457a902a4a86dfeca584
Akademický článek
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Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 3, Pp 466-475 (2017)
Coolant mixing under natural circulation flow regime constitutes a key parameter that may play a role in the course of an accidental transient in a nuclear pressurized water reactor. This issue has motivated some experimental investigations carried o
Externí odkaz:
https://doaj.org/article/9de04621ee4e40a6ad51d9b287448360
Akademický článek
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Autor:
Thomas Höhne, Sören Kliem
Publikováno v:
Fluids 8(2023)1, 4
Fluids; Volume 8; Issue 1; Pages: 4
Fluids; Volume 8; Issue 1; Pages: 4
The development, verification, and validation of Computational Fluid Dynamics (CFD) codes in reference to nuclear power plant (NPP) safety has been a focus of many research organizations over the last few decades. Therefore, a collection of Rossendor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::84cf0e64803b6579acdde1a6e93d6d80
https://www.hzdr.de/publications/Publ-31594-1
https://www.hzdr.de/publications/Publ-31594-1
Publikováno v:
New Zealand Management. Dec2001, Vol. 48 Issue 11, p120. 1/4p.