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Thermal–hydraulic modeling of reactivity insertion in a research reactor

https://doi.org/10.1016/j.anucene.2012.02.017

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What this work says

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

inferredcites →https://doi.org/10.1016/0140-6701(95)95486-oopenalex-snapshot

95/03868 Convective boiling and condensation

inferredcites →https://doi.org/10.1016/j.anucene.2004.03.008openalex-snapshot

Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code

inferredcites →https://doi.org/10.1016/j.anucene.2005.11.002openalex-snapshot

Reactivity insertion limits in a typical pool-type research reactor cooled by natural circulation

inferredcites →https://doi.org/10.1016/j.anucene.2008.05.006openalex-snapshot

Thermal-hydraulic modeling of flow inversion in a research reactor

inferredcites →https://doi.org/10.1016/j.anucene.2008.11.038openalex-snapshot

Development of a thermal–hydraulic analysis code for research reactors with plate fuels

inferredcites →https://doi.org/10.1016/j.nucengdes.2007.02.014openalex-snapshot

The 2006 CHF look-up table

inferredcites →https://doi.org/10.1016/s0306-4549(01)00107-4openalex-snapshot

Lumped parameters analysis of coupled kinetics and thermal-hydraulics for small reactors

inferredcites →https://doi.org/10.1021/ed032p167.3openalex-snapshot

Introduction to nuclear engineering

inferredcites →https://doi.org/10.1063/1.3037597openalex-snapshot

Introduction to Nuclear Engineering

inferredcites →https://doi.org/10.1093/oso/9780198562825.001.0001openalex-snapshot

Convective Boiling and Condensation

inferredcites →https://doi.org/10.1137/1.9781611973242openalex-snapshot

The Method of Weighted Residuals and Variational Principles

inferredcites →https://doi.org/10.13182/nse89-a23663openalex-snapshot

On the Numerical Solution of the Point Reactor Kinetics Equations by Generalized Runge-Kutta Methods

inferredcites →https://doi.org/10.13182/nt84-a33342openalex-snapshot

A Kinetics and Thermal-Hydraulics Capability for the Analysis of Research Reactors

inferredcites →https://doi.org/10.2172/4812807openalex-snapshot

PARET: A PROGRAM FOR THE ANALYSIS OF REACTOR TRANSIENTS.

inferredcites →https://doi.org/10.2172/7359476openalex-snapshot

COBRA-IV-I: an interim version of COBRA for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores

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.4669103openalex-extracted

Deterministic and Stochastic Computational Models for the Analysis of Nuclear Power Plant (Npp) Start-Up Operations

inferred← citeshttps://doi.org/10.1016/j.anucene.2020.107449openalex-snapshot

Transient analysis of the Brazilian Multipurpose Reactor by the coupled neutronics and thermal hydraulics code NTHC1

inferred← citeshttps://doi.org/10.1016/j.anucene.2020.107545openalex-snapshot

The development of TM2-RIA code for TRIGA type research reactors

inferred← citeshttps://doi.org/10.1016/j.net.2019.11.011openalex-snapshot

Performance evaluation of the Floating Absorber for Safety at Transient (FAST) in the innovative Sodium-cooled Fast Reactor (iSFR) under a single control rod withdrawal accident

inferred← citeshttps://doi.org/10.1016/j.nucengdes.2024.113543openalex-snapshot

Deterministic and stochastic computational models for the analysis of Nuclear Power Plant (NPP) start-up operations

inferred← citeshttps://doi.org/10.1016/j.pnucene.2018.02.009openalex-snapshot

Investigation of flapper valve malfunction in Tehran Research Reactor with porous media model

inferred← citeshttps://doi.org/10.11591/ijeecs.v20.i2.pp788-797openalex-snapshot

TRIGA PUSPATI reactor: model analysis and accuracy

inferred← citeshttps://doi.org/10.17146/aij.2018.545openalex-snapshot

Dynamic Analysis on the Safety Criteria of the Conceptual Core Design in MTR-type Research Reactor

inferred← citeshttps://doi.org/10.17146/aij.2019.810openalex-snapshot

Calculation of Control Rods Reactivity Worth of RSG-GAS First Core Using Deterministic and Monte Carlo Methods

inferred← citeshttps://doi.org/10.17146/gnd.2020.23.2.5876openalex-snapshot

ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE TYPE FUEL ELEMENT

inferred← citeshttps://doi.org/10.17146/tdm.2021.23.2.6278openalex-snapshot

Analysis of Neutron Absorber Materials on the Safety Parameters in the RSG-GAS Reactor

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