Steady-State Thermal-Hydraulic Analysis of TRIGA Research Reactor

Journals Menu

Follow SCIRP

	+1 323-425-8868
	customer@scirp.org
	+86 18163351462(WhatsApp)
	1655362766

	Paper Publishing WeChat

World Journal of Nuclear Science and Technology

ISSN Print: 2161-6795
ISSN Online: 2161-6809
www.scirp.org/journal/wjnst
E-mail: wjnst@scirp.org

Citations h5-index & Ranking

Journals Menu

"Steady-State Thermal-Hydraulic Analysis of TRIGA Research Reactor"
written by Mohammad Mizanur Rahman, Mohammad Abdur R. Akond, Mohammad Khairul Basher, Md. Quamrul Huda,
published by World Journal of Nuclear Science and Technology, Vol.4 No.2, 2014

has been cited by the following article(s):

Google Scholar
CrossRef

[1]	Analysis of DNBR TRIGA 2000 calculation results using STAT and COOLOD-N2
	AIP Conference Proceedings, 2021

[2]	Steady-state Thermal-hydraulic Analysis of the TRIGA 2000 Reactor Core when Using Configuration of 105 Fuels
	2020

[3]	Steady-State Safety Analysis of Ghana Research Reactor-1 With Low-Enriched-Uranium Core
	2020

[4]	Thermal-hydraulic analysis of fuel rod of a TRIGA Mark II research reactor
	2020

[5]	Steady State Safety Analysis of Ghana Research Reactor− 1 (GHARR-1) with LEU Core
	2020

[6]	Experimental Analysis on Safety System of a Simulated Small Scale Pressurized Water Reactor System with Intelligent Control
	2020

[7]	OPTIMALISASI DAYA REAKTOR TRIGA 2000 DENGAN KONFIGURASI TERAS 110 BAHAN BAKAR
	Prosiding Seminar Nasional Infrastruktur Energi Nuklir, 2019

[8]	Optimization of TRIGA 2000 reactor power with 110 fuel configuration
	2019

[9]	Thermal Hydraulic Analysis of Low Enriched Uranium (LEU) Core of the Ghana Research Reactor-1 (GHARR-1)
	2019

[10]	Heat removal analysis in the AP1000 reactor's refuelling process
	2019

[11]	Steady-state thermal-hydraulic analysis of the TRIGA plate core design by using COOLOD-N2 and RELAP5 codes
	2019

[12]	Calculation of Control Rod Worth of TRIGA Mark II Reactor Using Evaluated Nuclear Data Library JEFF-3.1. 2
	IOSR Journal of Applied Physics, 2018

[13]	Thermal Hydraulics Simulation of Fuel Sub-Assembly for 1200 MWe Nuclear Power Reactor
	2018

[14]	Estimation of Na-24 activity concentration in BAEC TRIGA Research Reactor
	Results in Physics, 2017

[15]	Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor
	Applied Radiation and Isotopes, 2017

[16]	ASSESSMENT OF N-16 ACTIVITY CONCENTRATION IN BANGLADESH ATOMIC ENERGY COMMISSION TRIGA RESEARCH REACTOR
	Nuclear Engineering and Technology, 2017

[17]	Fundamental approaches for analysis thermal hydraulic parameter for Puspati Research Reactor
	ADVANCING NUCLEAR SCIENCE AND ENGINEERING FOR SUSTAINABLE NUCLEAR ENERGY INFRASTRUCTURE: Proceeding of the International Nuclear Science, Technology and Engineering Conference 2015 (iNuSTEC2015), 2016

[18]	ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI
	TRI DASA MEGA-Jurnal Teknologi Reaktor Nuklir, 2015

[1]	Optimization for fuel loading and reactivity initiated accident analysis for TRR-1/M1 Journal of Physics: Conference Series, 2023 DOI:10.1088/1742-6596/2431/1/012077

[2]	Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor Annals of Nuclear Energy, 2023 DOI:10.1016/j.anucene.2023.110020

[3]	Analysis of nuclear fuel rod temperature distribution using CFD calculation and analytical solution PROCEEDINGS OF THE 6TH INTERNATIONAL SYMPOSIUM ON CURRENT PROGRESS IN MATHEMATICS AND SCIENCES 2020 (ISCPMS 2020), 2021 DOI:10.1063/5.0058888

[4]	Analysis of DNBR TRIGA 2000 calculation results using STAT and COOLOD-N2 PROCEEDINGS OF INTERNATIONAL CONFERENCE ON NUCLEAR SCIENCE, TECHNOLOGY, AND APPLICATION 2020 (ICONSTA 2020), 2021 DOI:10.1063/5.0067845

[5]	Steady-state Thermal-hydraulic Analysis of the TRIGA 2000 Reactor Core when Using Configuration of 105 Fuels Journal of Physics: Conference Series, 2020 DOI:10.1088/1742-6596/1436/1/012091

[6]	Steady-State Safety Analysis of Ghana Research Reactor-1 With Low-Enriched-Uranium Core Journal of Thermal Science and Engineering Applications, 2020 DOI:10.1115/1.4046598

[7]	Heat removal analysis in the AP1000 reactor’s refuelling process Journal of Physics: Conference Series, 2019 DOI:10.1088/1742-6596/1198/2/022066

[8]	Steady-state thermal-hydraulic analysis of the TRIGA plate core design by using COOLOD-N2 and RELAP5 codes THE 4TH BIOMEDICAL ENGINEERING’S RECENT PROGRESS IN BIOMATERIALS, DRUGS DEVELOPMENT, HEALTH, AND MEDICAL DEVICES: Proceedings of the International Symposium of Biomedical Engineering (ISBE) 2019, 2019 DOI:10.1063/1.5135526

[9]	Estimation of Na-24 activity concentration in BAEC TRIGA Research Reactor Results in Physics, 2017 DOI:10.1016/j.rinp.2017.02.014

[10]	Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor Applied Radiation and Isotopes, 2017 DOI:10.1016/j.apradiso.2017.09.001

[11]	ASSESSMENT OF N-16 ACTIVITY CONCENTRATION IN BANGLADESH ATOMIC ENERGY COMMISSION TRIGA RESEARCH REACTOR Nuclear Engineering and Technology, 2017 DOI:10.1016/j.net.2017.11.006

[12]	Estimation of Na-24 activity concentration in BAEC TRIGA Research Reactor Results in Physics, 2017 DOI:10.1016/j.rinp.2017.02.014

[13]	Fundamental approaches for analysis thermal hydraulic parameter for Puspati Research Reactor 2016 DOI:10.1063/1.4940064

Follow SCIRP

	+1 323-425-8868
	customer@scirp.org
	+86 18163351462(WhatsApp)
	1655362766

	Paper Publishing WeChat

World Journal of Nuclear Science and Technology

World Journal of Nuclear Science and Technology

Journals Menu

Home

About SCIRP

Service

Policies