Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM

K Skolik, C Allison, J Hohorst, M Malicki… - Progress in Nuclear …, 2021 - Elsevier
Abstract Small Modular Reactors (SMRs) are currently being developed and licensed in
many countries. The innovations in the designs provide many significant features, such as …

Role of RELAP/SCDAPSIM in nuclear safety

CM Allison, JK Hohorst - Science and technology of Nuclear …, 2010 - Wiley Online Library
The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during
normal and accident conditions, is being developed as part of the international SCDAP …

Passive cooling system in a nuclear spent fuel pool using a vertical straight wickless-heat pipe

MH Kusuma, N Putra, AR Antariksawan… - International Journal of …, 2018 - Elsevier
To enhance the thermal safety when a station blackout accident occurs, a vertical, straight,
wickless-heat pipe is proposed as a passive residual heat removal system on the nuclear …

Thermal hydraulic analysis of the IPR-R1 TRIGA research reactor using a RELAP5 model

AL Costa, PAL Reis, C Pereira, MAF Veloso… - … Engineering and Design, 2010 - Elsevier
The RELAP5 code is widely used for thermal hydraulic studies of commercial nuclear power
plants. Current investigations and code adaptations have demonstrated that the RELAP5 …

Assessment of a RELAP5 model for the IPR-R1 TRIGA research reactor

PAL Reis, AL Costa, C Pereira, MAF Veloso… - Annals of Nuclear …, 2010 - Elsevier
RELAP5 code was developed at the Idaho National Environmental and Engineering
Laboratory and it is widely used for thermal hydraulic studies of commercial nuclear power …

Sensitivity analysis to a RELAP5 nodalization developed for a typical TRIGA research reactor

PAL Reis, AL Costa, C Pereira, CAM Silva… - … Engineering and Design, 2012 - Elsevier
The main aim of this work is to identify how much the code results are affected by the code
user in the choice of, for example, the number of thermal hydraulic channels in a nuclear …

Analysis of loss of flow events on brazilian multipurpose reactor using the relap5 code

HV Soares, ID Aronne, AL Costa… - … Journal of Nuclear …, 2014 - Wiley Online Library
This work presents the thermal hydraulic simulation of the Brazilian multipurpose reactor
(RMB) using a RELAP5/MOD3. 3 model. Beyond steady state calculations, three transient …

[PDF][PDF] TRIGA 2000 Research Reactor Thermal-hydraulic Analysis Using RELAP/SCDAPSIM/MOD3. 4

AR Antariksawan, E Umar, S Widodo… - International Journal …, 2017 - researchgate.net
Any events presumed to risk the safety of a nuclear reactor should be analyzed. In a
research reactor, the applicability of best estimate thermal-hydraulic codes has been …

NUR research reactor safety analysis study for long time natural convection (NC) operation mode

M Azzoune, L Mammou, MH Boulheouchat… - … Engineering and Design, 2010 - Elsevier
The current work represents a part of an overall effort being undertaken to improve NUR
nuclear research reactor neutron utilization capabilities using a new core configuration. A …

Benchmarking COMSOL Multiphysics Single‐Subchannel Thermal‐Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data

AK Alkaabi, JC King - Science and Technology of Nuclear …, 2019 - Wiley Online Library
COMSOL Multiphysics has been used to conduct thermal‐hydraulic analysis in multiple
nuclear applications. The aim of this study is to benchmark the prediction accuracy of …