A network approach to full core temperature analysis in advanced nuclear heat-pipe systems

Mueller, Cole; Tsvetkov, Pavel

doi:10.1016/j.anucene.2021.108354

Title: A network approach to full core temperature analysis in advanced nuclear heat-pipe systems

Journal Article · 01 September 2021 · Annals of Nuclear Energy

DOI: https://doi.org/10.1016/j.anucene.2021.108354 · OSTI ID:1818557

Mueller, Cole; Tsvetkov, Pavel

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Sponsoring Organization:: USDOE

OSTI ID:: 1818557

Journal Information:: Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Journal Issue: C Vol. 160; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United Kingdom

Language:: English

References (13)

Transient lumped heat pipe analyses Faghri, Amir; Harley, Charles Heat Recovery Systems and CHP, Vol. 14, Issue 4 https://doi.org/10.1016/0890-4332(94)90039-6	journal	July 1994
A network thermodynamic analysis of the heat pipe Zuo, Z. J.; Faghri, A. International Journal of Heat and Mass Transfer, Vol. 41, Issue 11 https://doi.org/10.1016/S0017-9310(97)00220-2	journal	June 1998
The technology of micro heat pipe cooled reactor: A review Yan, B. H.; Wang, C.; Li, L. G. Annals of Nuclear Energy, Vol. 135 https://doi.org/10.1016/j.anucene.2019.106948	journal	January 2020
Novel design integration for advanced nuclear heat-pipe systems Mueller, Cole; Tsvetkov, Pavel Annals of Nuclear Energy, Vol. 141 https://doi.org/10.1016/j.anucene.2020.107324	journal	June 2020
Lumped parameter model of sintered heat pipe: Transient numerical analysis and validation Ferrandi, C.; Iorizzo, F.; Mameli, M. Applied Thermal Engineering, Vol. 50, Issue 1 https://doi.org/10.1016/j.applthermaleng.2012.07.022	journal	January 2013
A pure-conduction transient model for heat pipes via derivation of a pseudo wick thermal conductivity Ma, Mingyang; Liang, Wenfeng; Wang, Shumiao International Journal of Heat and Mass Transfer, Vol. 149 https://doi.org/10.1016/j.ijheatmasstransfer.2019.119122	journal	March 2020
Two stochastic optimization algorithms applied to nuclear reactor core design Sacco, Wagner F.; de oliveira, Cassiano R. E.; Pereira, Cláudio M. N. A. Progress in Nuclear Energy, Vol. 48, Issue 6 https://doi.org/10.1016/j.pnucene.2005.10.004	journal	August 2006
Particle Swarm Optimization applied to the nuclear reload problem of a Pressurized Water Reactor Meneses, Anderson Alvarenga de Moura; Machado, Marcelo Dornellas; Schirru, Roberto Progress in Nuclear Energy, Vol. 51, Issue 2 https://doi.org/10.1016/j.pnucene.2008.07.002	journal	March 2009
Small modular reactor full scope core optimization using Cuckoo Optimization Algorithm Akbari, R.; Rezaei Ochbelagh, D.; Gharib, A. Progress in Nuclear Energy, Vol. 122 https://doi.org/10.1016/j.pnucene.2020.103271	journal	April 2020
Optimization of Pressurized Water Reactor Shuffling by Simulated Annealing with Heuristics Stevens, J. G.; Smith, K. S.; Rempe, K. R. Nuclear Science and Engineering, Vol. 121, Issue 1 https://doi.org/10.13182/NSE121-67	journal	September 1995
Design of megawatt power level heat pipe reactors Mcclure, Patrick Ray; Poston, David Irvin; Dasari, Venkateswara Rao Report - Los Alamos National Laboratory https://doi.org/10.2172/1226133	report	November 2015
Preliminary Assessment of Two Alternative Core Design Concepts for the Special Purpose Reactor Sterbentz, James W.; Werner, James E.; Hummel, Andrew J. https://doi.org/10.2172/1413987	report	November 2017
Simple Conduction Model for Theoretical Steady-State Heat Pipe Performance Sun, K. H.; Tien, C. L. AIAA Journal, Vol. 10, Issue 8 https://doi.org/10.2514/3.50293	journal	August 1972

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