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H. Glaeser
Observed names:
GLAESER H,
Glaeser, H.,
H Glaeser,
H. GLAESER,
Horst G. Glaeser,
Horst Glaeser
show all 6
Observed institution:
Gesellschaft für Anlagen und Reaktorsicherheit
OpenAlex ID:
A5086593005
GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications
2008
·
Horst Glaeser
·
Science and Technology of Nuclear Installations
·
245
PDF
Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme
2011
·
M. Perez
, F. Reventos
, et al.
·
Nuclear Engineering and Design
·
89
Uncertainty and sensitivity analysis of a post-experiment calculation in thermal hydraulics
1994
·
H. Glaeser
, E. Hofer
, et al.
·
Reliability Engineering & System Safety
·
79
Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme
2008
·
A. de Crécy
, P. Bazin
, et al.
·
Nuclear Engineering and Design
·
74
Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. IAEA Safety Report Series
2008
·
Francesco Saverio D'Auria
, H. Glaeser
, et al.
·
CERN Document Server (European Organization for Nuclear Research)
·
53
PDF
Downcomer and tie plate countercurrent flow in the Upper Plenum Test Facility (UPTF)
1992
·
Horst Glaeser
·
Nuclear Engineering and Design
·
43
Thermal-hydraulic phenomena for water cooled nuclear reactors
2018
·
N. Aksan
, F. D'Auria
, et al.
·
Nuclear Engineering and Design
·
39
The contribution of UPTF experiments to resolve some scale-up uncertainties in countercurrent two phase flow
1993
·
H Glaeser
, H Karwat
·
Nuclear Engineering and Design
·
29
Strengthening nuclear reactor safety and analysis
2017
·
F. D'Auria
, N. Debrecin
, et al.
·
Nuclear Engineering and Design
·
28
Combining Insights from Probabilistic and Deterministic Safety Analyses in Option 4 from the IAEA Specific Safety Guide SSG-2
2014
·
Milorad Dusic
, Mark Dutton
, et al.
·
Nuclear Technology
·
27
The technological challenge for current generation nuclear reactors
2019
·
Francesco D’Auria
, Nenad Debrecin
, et al.
·
Nuclear Energy and Technology
·
20
PDF
Verification and validation of system thermal-hydraulic computer codes, scaling and uncertainty evaluation of calculated code results
2017
·
H. Glaeser
·
Elsevier eBooks
·
18
Overview of Uncertainty Issues and Methodologies
1998
·
Francesco Saverio D'Auria
, E. Chojnacki
, et al.
·
CINECA IRIS Institutial research information system (University of Pisa)
·
18
Deterministic Safety Analysis for Nuclear Power Plants. IAEA Specific Safety Guide
2009
·
Francesco Saverio D'Auria
, M. Dusic
, et al.
·
CINECA IRIS Institutial research information system (University of Pisa)
·
17
PDF
Main Results of Phase IV BEMUSE Project: Simulation of LBLOCA in an NPP
2010
·
M. Pérez
, F. Reventós
, et al.
·
Science and Technology of Nuclear Installations
·
13
PDF
Scaling ability of the counter-current flow limitation (CCFL) correlations for application to reactor thermal hydraulics
2019
·
Horst Glaeser
, Upendra Singh Rohatgi
·
Nuclear Engineering and Design
·
12
PDF
Report on the Uncertainty Methods Study
1998
·
David Sweet
, Andrew Neill
, et al.
·
11
Report of the Uncertainty Methods Study for advanced best estimate thermalhydraulic code applications
1998
·
T. Wickett
, Francesco Saverio D'Auria
, et al.
·
10
Independent assessment for new nuclear reactor safety
2017
·
Francesco D'Auria
, Horst Glaeser
, et al.
·
EPJ Nuclear Sciences & Technologies
·
9
PDF
A vision for nuclear reactor safety
2015
·
Francesco Saverio D'Auria
, H. Glaeser
, et al.
·
CINECA IRIS Institutial research information system (University of Pisa)
·
9
BEMUSE Phase V Report Uncertainty and Sensitivity Analysis of a LBLOCA in Zion Nuclear Power Plant. OECD/NEA Report
2009
·
F. Reventós
, B. M.
, et al.
·
9
New Safety Barrier for Current and Future Nuclear Reactors
2018
·
Francesco Saverio D'Auria
, Nenad Debrecin
, et al.
·
6
Physical Phenomena in Nuclear Thermal Hydraulics and Current Status
2021
·
F. D’Auria
, N. Aksan
, et al.
·
TECNICA ITALIANA-Italian Journal of Engineering Science
·
5
PDF
Uncertainty and Sensitivity Analysis for a Nuclear Power Plant Large Break Loss of Coolant Accident (LB-LOCA) in the Context of OECD BEMUSE Programme
2011
·
F. Reventós
, H. Glaeser
, et al.
·
5
Further evaluation of the CSNI separate effect test activity
1995
·
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology
, F. D`Auria
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
5
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Works count:
75
Citation count:
912
H-index:
14
I10-index:
18
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