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Keyword

RELAP5

Description: A computer code for simulating thermal-hydraulic behavior in nuclear reactor systems, used in reactor safety analysis.
Wikidata ID: wiki/Q7276340
OpenAlex ID: keywords/relap5
High performance light water reactor
2003 · D. Squarer, T. Schulenberg, et al. · Nuclear Engineering and Design · 143
Modelling of Two-Phase Flow with Second-Order Accurate Scheme
1997 · Iztok Tiselj, Stojan Petelin · Journal of Computational Physics · 114
Transient and stability analysis in single-phase natural circulation
2004 · Seyed Khalil Mousavian, Mario Misale, et al. · Annals of Nuclear Energy · 110
Reliability evaluation of a natural circulation system
2003 · Jalil Jafari, Francesco D’Auria, et al. · Nuclear Engineering and Design · 97
Experimental and theoretical study of steam condensation induced water hammer phenomena
2009 · Imre Ferenc Barna, Attila Rikárd Imre, et al. · Nuclear Engineering and Design · 96
Comparative study of data-driven and model-driven approaches in prediction of nuclear power plants operating parameters
2023 · Houde Song, Xiaojing Liu, et al. · Applied Energy · 83
Diagnostic system for identification of accident scenarios in nuclear power plants using artificial neural networks
2008 · T.V. Santosh, A. Srivastava, et al. · Reliability Engineering & System Safety · 77
Investigation of a long term passive cooling system using two-phase thermosyphon loops for the nuclear reactor spent fuel pool
2015 · Wen Fu, Xiaowei Li, et al. · Annals of Nuclear Energy · 75
Discussion on the stability of heated channels with different fluids at supercritical pressures
2009 · Walter Ambrosini · Nuclear Engineering and Design · 57
Modelling of low-pressure subcooled flow boiling using the RELAP5 code
2003 · Boštjan Končar, Borut Mavko · Nuclear Engineering and Design · 54
Analysis of different containment models for IRIS small break LOCA, using GOTHIC and RELAP5 codes
2010 · Davide Papini, Davor Grgić, et al. · Nuclear Engineering and Design · 51
Development and application of a system analysis code for liquid fueled molten salt reactors based on RELAP5 code
2016 · Chengbin Shi, Maosong Cheng, et al. · Nuclear Engineering and Design · 49
The use of multi-objective optimization to improve the design process of nuclear power plant systems
2019 · Paul R. Wilding, Nathan R. Murray, et al. · Annals of Nuclear Energy · 47
The design of a compact integral medium size PWR
2011 · Koroush Shirvan, Pavel Hejzlar, et al. · Nuclear Engineering and Design · 46
Pseudo material construct for coupled neutronic-thermal-hydraulic analysis of VHTGR
2005 · Jeremy Conlin, Wei Ji, et al. · Transactions of the American Nuclear Society · 45
Discussion on the stability of natural circulation loops with supercritical pressure fluids
2012 · Seth Kofi Debrah, Walter Ambrosini, et al. · Annals of Nuclear Energy · 43
Time-domain linear and non-linear studies on density wave oscillations
2012 · Davide Papini, Antonio Cammi, et al. · Chemical Engineering Science · 43
Regularization of Two-Phase Flow Models: A Comparison of Numerical and Differential Approaches
1997 · Himanshu Pokharna, Michitsugu Mori, et al. · Journal of Computational Physics · 43
Design of passive residual heat removal systems and application of two-phase thermosyphons: A review
2022 · Widodo Surip, Nandy Putra, et al. · Progress in Nuclear Energy · 42
Thermal–hydraulics system codes uncertainty assessment: A review of the methodologies
2009 · Mohammad Pourgol-Mohammad · Annals of Nuclear Energy · 42
Integrated framework for model assessment and advanced uncertainty quantification of nuclear computer codes under Bayesian statistics
2019 · Majdi I. Radaideh, Katarzyna Borowiec, et al. · Reliability Engineering & System Safety · 41
Design and application of supervisory control based on neural network PID controllers for pressurizer system
2020 · Seyed Ali Hosseini, Amir Saeed Shirani, et al. · Progress in Nuclear Energy · 40
State-of-the-art computer code RELAP5 validation with RBMK-related separate phenomena data
2003 · Rolandas Urbonas, Eugenijus Uspuras, et al. · Nuclear Engineering and Design · 40
Analysis of the processes in spent fuel pools of Ignalina NPP in case of loss of heat removal
2010 · А. Кaliatka, V. Оgnerubov, et al. · Nuclear Engineering and Design · 39
Use of an ideal scaled model for scaling evaluation
1998 · V.H Ransom, W Wang, et al. · Nuclear Engineering and Design · 39
Works count: 1,584
Citation count: 6,527
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