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Critical Heat Flux in TRIGA-Fueled Reactors Cooled by Natural Convection

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What this work says

Outgoing claims: the papers this work cites, builds on, or argues with.

inferredcites →https://doi.org/10.1016/0017-9310(78)90009-1openalex-snapshot

A generalized correlation of critical heat flux for the forced convection boiling in vertical uniformly heated round tubes

inferredcites →https://doi.org/10.1016/0017-9310(88)90161-5openalex-snapshot

Experimental studies of critical heat flux for low flow of water in vertical annuli at near atmospheric pressure

inferredcites →https://doi.org/10.1016/0017-9310(93)80008-iopenalex-snapshot

Critical heat flux for low flow boiling in vertical uniformly heated thin rectangular channels

inferredcites →https://doi.org/10.1016/0029-5493(67)90049-0openalex-snapshot

A correlation for the minima in the pressure drop versus flow-rate curves for sub-cooled water flowing in narrow heated channels

inferredcites →https://doi.org/10.1016/0029-5493(94)90283-6openalex-snapshot

A comparison of critical heat flux in tubes and annuli

inferredcites →https://doi.org/10.1016/0029-5493(95)01154-4openalex-snapshot

The 1995 look-up table for critical heat flux in tubes

inferredcites →https://doi.org/10.1016/j.ijmultiphaseflow.2009.07.004openalex-snapshot

Experimental study on critical heat flux in bilaterally heated narrow annuli

inferredcites →https://doi.org/10.1016/s0029-5493(97)00032-0openalex-snapshot

Critical heat flux and flow pattern for water flow in annular geometry

inferredcites →https://doi.org/10.1115/1.1725101openalex-snapshot

Critical Heat Fluxes of Subcooled Water Flow Boiling Against Outlet Subcooling in Short Vertical Tube

inferredcites →https://doi.org/10.1115/1.2910695openalex-snapshot

A New CHF Correlation Scheme Proposed for Vertical Rectangular Channels Heated From Both Sides in Nuclear Research Reactors

What points at this work

Incoming claims: where this work appears in other papers’ reference lists and arguments.

inferred← citeshttps://doi.org/10.2139/ssrn.4139402openalex-extracted

inferred← citeshttps://doi.org/10.1016/j.anucene.2019.107153openalex-snapshot

Razorback – A reactor transient analysis code for large rapid reactivity additions in a natural circulation research reactor

inferred← citeshttps://doi.org/10.1016/j.anucene.2023.110020openalex-snapshot

Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor

inferred← citeshttps://doi.org/10.1016/j.apradiso.2025.111885openalex-snapshot

Development of a new steady-state thermal hydraulic and safety analysis code, OpenTHY, for a TRIGA MARK II research reactor

inferred← citeshttps://doi.org/10.1016/j.nucengdes.2022.112118openalex-snapshot

A Complete Cfd Study on Natural Convection in the Triga Mark Ii Reactor

inferred← citeshttps://doi.org/10.1016/j.nucengdes.2024.113092openalex-snapshot

Neutronic and thermal-hydraulic analysis for TRIGA Mark II in subcooled nucleate boiling condition

inferred← citeshttps://doi.org/10.1016/j.nucengdes.2026.115056openalex-snapshot

Three-dimensional CFD analysis of turbulence modeling and temperature-dependent thermophysical properties in a TRIGA mark II fuel rod

inferred← citeshttps://doi.org/10.1063/5.0193245openalex-snapshot

Experimental study of natural circulation in Kartini reactor core: Effect of primary flow rate and power

inferred← citeshttps://doi.org/10.1155/2013/950129openalex-snapshot

Detection of the Departure from Nucleate Boiling in Nuclear Fuel Rod Simulators

inferred← citeshttps://doi.org/10.17146/tdm.2020.22.2.5888openalex-snapshot

Bandung TRIGA 2000 Reactor Power Analysis as a Function of the Number of Fuel Elements and the Power Peaking Factor

inferred← citeshttps://doi.org/10.2172/1155132openalex-snapshot

Summary of RELAP5 Assessments Performed in Relation to Conversion Analysis of Research Reactors

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