Semi-two-dimensional transient modeling of decay heat removal to an external reactor cavity cooling system for a gFHR with effects of heat generation pattern

Talaat, Khaled; Chen, Minghui

doi:10.1016/j.nucengdes.2024.112956

Title: Semi-two-dimensional transient modeling of decay heat removal to an external reactor cavity cooling system for a gFHR with effects of heat generation pattern

Journal Article · 01 April 2024 · Nuclear Engineering and Design

DOI: https://doi.org/10.1016/j.nucengdes.2024.112956 · OSTI ID:2283102

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Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: NE0009254

OSTI ID:: 2283102

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 419 Journal Issue: C; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: Netherlands

Language:: English

References (23)

Scaling analysis for the direct reactor auxiliary cooling system for FHRs Lv, Q.; Wang, X.; Kim, I. H. Nuclear Engineering and Design, Vol. 285 https://doi.org/10.1016/j.nucengdes.2014.12.035	journal	April 2015
Passive heat removal impact on AREVA HTR design Lommers, L. J.; Mays, B. E.; Shahrokhi, F. Nuclear Engineering and Design, Vol. 271 https://doi.org/10.1016/j.nucengdes.2013.12.034	journal	May 2014
Outlook for MHTGR project development Hoffman, D. P.; Mears, L. D. Energy, Vol. 16, Issue 1-2 https://doi.org/10.1016/0360-5442(91)90090-9	journal	January 1991
Design Report for the ½ Scale Air-Cooled RCCS Tests in the Natural convection Shutdown heat removal Test Facility (NSTF) Lisowski, D. D.; Farmer, M. T.; Lomperski, S. https://doi.org/10.2172/1184668	report	June 2014
RCCS Testing with the Water-based NSTF: Year-1 Single-Phase Results Lisowski, D.; Lv, Q.; Hu, R. https://doi.org/10.2172/1558600	report	August 2019
Computational Fluid Dynamics Analysis of Very High Temperature Gas-Cooled Reactor Cavity Cooling System Frisani, Angelo; Hassan, Yassin A.; Ugaz, Victor M. Nuclear Technology, Vol. 176, Issue 2 https://doi.org/10.13182/NT11-A13299	journal	November 2011
Study on the Behavior of an Asymmetrically Heated Reactor Cavity Cooling System with Water in Single Phase Lisowski, D. D.; Haskin, T. C.; Tokuhiro, A. Nuclear Technology, Vol. 183, Issue 1 https://doi.org/10.13182/NT13-A16993	journal	July 2013
Scaling Analysis of Reactor Cavity Cooling System in HTR Roberto, Thiago D.; Lapa, Celso M. F.; Alvim, Antonio C. M. Nuclear Technology, Vol. 206, Issue 4 https://doi.org/10.1080/00295450.2019.1666603	journal	December 2019
Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility Lv, Q.; Lin, H. C.; Shi, S. Nuclear Technology, Vol. 196, Issue 2 https://doi.org/10.13182/NT16-41	journal	November 2016
Experimental measurement and numerical modeling of the effective thermal conductivity of TRISO fuel compacts Folsom, Charles; Xing, Changhu; Jensen, Colby Journal of Nuclear Materials, Vol. 458 https://doi.org/10.1016/j.jnucmat.2014.12.042	journal	March 2015
Report on Year-2 of Water NSTF Matrix Testing Lisowski, Darius; Lv, Qiuping; Bremer, Nathan https://doi.org/10.2172/1782658	report	September 2020
An Overview of Non-LWR Vessel Cooling Systems for Passive Decay Heat Removal (Technical Letter Final Report) Lisowski, Darius; Lv, Qiuping; Alexandreanu, Bogdan https://doi.org/10.2172/1786964	report	May 2021
Separate effects tests to determine the effective thermal conductivity in the PBMR HTTU test facility Rousseau, P. G.; du Toit, C. G.; van Antwerpen, W. Nuclear Engineering and Design, Vol. 271 https://doi.org/10.1016/j.nucengdes.2013.12.015	journal	May 2014
A review of correlations to model the packing structure and effective thermal conductivity in packed beds of mono-sized spherical particles van Antwerpen, W.; du Toit, C. G.; Rousseau, P. G. Nuclear Engineering and Design, Vol. 240, Issue 7 https://doi.org/10.1016/j.nucengdes.2010.03.009	journal	July 2010
Final Project Report on RCCS Testing with Air-based NSTF Lisowski, Darius D.; Gerardi, Craig D.; Kilsdonk, Dennis J. https://doi.org/10.2172/1350591	report	August 2016
Progress on Computational Modeling of Water-Based NSTF (FY2021) Lv, Q.; Kraus, A.; Ooi, Z. J. https://doi.org/10.2172/1825925	report	September 2021
Evaluation and optimization of General Atomics’ GT-MHR reactor cavity cooling system using an axiomatic design approach Thielman, Jeff; Ge, Ping; Wu, Qiao Nuclear Engineering and Design, Vol. 235, Issue 13 https://doi.org/10.1016/j.nucengdes.2004.11.015	journal	June 2005
Water NSTF Design, Instrumentation, and Test Planning Lisowski, Darius D.; Gerardi, Craig D.; Hu, Rui https://doi.org/10.2172/1375452	report	August 2017
Design of a prototypical natural circulation water-based reactor cavity cooling system (RCCS) for a pebble-bed generic FHR Talaat, Khaled; Chen, Minghui Nuclear Engineering and Design, Vol. 407 https://doi.org/10.1016/j.nucengdes.2023.112303	journal	June 2023
Reactor cavity cooling system (Rccs) experimental characterization Capone, Luigi; Hassan, Yassin A.; Vaghetto, Rodolfo Nuclear Engineering and Design, Vol. 241, Issue 12 https://doi.org/10.1016/j.nucengdes.2011.07.043	journal	December 2011
Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant Andreades, Charalampos; Cisneros, Anselmo T.; Choi, Jae Keun Nuclear Technology, Vol. 195, Issue 3 https://doi.org/10.13182/NT16-2	journal	September 2016
DRACS thermal performance evaluation for FHR Lv, Q.; Lin, H. C.; Kim, I. H. Annals of Nuclear Energy, Vol. 77 https://doi.org/10.1016/j.anucene.2014.10.032	journal	March 2015
Experimental Investigation of a Scaled Water-Cooled Reactor Cavity Cooling System Vaghetto, Rodolfo; Hassan, Yassin A. Nuclear Technology, Vol. 187, Issue 3 https://doi.org/10.13182/NT13-130	journal	September 2014

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