Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5–3D

Batet, L.; Alvarez-Fernandez, J.M.; Valls, E. Mas de les; Martinez-Quiroga, V.; Pérez, Montserrat; Reventós, F.; Sedano, L.

doi:10.1016/j.fusengdes.2014.03.018

Cited by 17 publications

(3 citation statements)

References 8 publications

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“…CATHARE, RELAP, TRACE, ATHLET, SCTRAN, and SAS4A/SASSYS-1 [5][6][7][8]. Because sCO 2 is considered a working fluid for 4th generation reactor concepts as well as for the proposed heat removal system, work is in progress to extend or couple these system codes for the simulation of sCO 2 power cycles [1,[7][8][9][10][11][12][13][14].…”

Section: Introductionmentioning

confidence: 99%

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO₂ heat removal system coupled to a pressurized water reactor

Hofer

Hecker²,

Buck

et al. 2022

EPJ Nuclear Sci. Technol.

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The supercritical carbon dioxide (sCO2) heat removal system, which is based on a closed Brayton cycle with sCO2 as a working fluid, is an innovative, self-propelling and modular heat removal system for existing and future nuclear power plants. By changing the number of CO2 cycles, the heat removal capacity can be adapted. In this paper, up to four sCO2 cycles are analyzed in interaction with a pressurized water reactor, using the thermal-hydraulic system code ATHLET and considering a long-term station blackout and loss of ultimate heat sink scenario with conservatively high and low decay heat curves. The presented start-up procedure for the heat removal system might require further optimization due to the non-linear thermal gradients. Independent from the start-up, a heat removal system with three or four CO2 cycles keeps the primary loop temperatures sufficiently low. However, with only three cycles, the core is almost uncovered, and the danger of recriticality may occur due to cold leg deboration. Controlling the turbine inlet temperature via the turbomachinery speed and subsequent shutdown of single cycles successfully adapts the operation of the heat removal system to the declining decay heat. This enables reliable decay heat removal for more than 72 h.

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Section: Introductionmentioning

confidence: 99%

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO₂ heat removal system coupled to a pressurized water reactor

Hofer

Hecker²,

Buck

et al. 2022

EPJ Nuclear Sci. Technol.

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show abstract

“…Idaho National Laboratory expanded the function of RELAP5-3D for next generation nuclear plant simulation and analysis. [29][30][31] The GFR proposed by Massachusetts Institute of Technology (MIT) 19 and nuclear fusion reactor designed under TECNO_FUS 32 was modeled and simulated by RELAP5-3D. The calculation capacity of the RELAP5-3D was verified and several typical transients were simulated to study the thermal-hydraulic characteristics of the SCO 2 -cooled reactor system.…”

Section: Introductionmentioning

confidence: 99%

Operation characteristic of supercritical carbon dioxide-cooled reactor system under coordination control scheme

Xia

2020

International Journal of Advanced Robotic Systems

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Nuclear power plant is completely independent of air and has high power density, which improves unmanned marine vehicle maneuvering performance, maximum speed, and concealment. The supercritical carbon dioxide-cooled reactor system that has the advantages of compact system and high cycle efficiency is a promising energy conversion system candidate for generation IV reactors. However, due to the dramatic variations of supercritical fluid thermophysical properties, the operation of supercritical carbon dioxide-cooled reactor system is complex and it is difficult to control it. In this article, a mathematical model of supercritical carbon dioxide-cooled reactor system was established using the modified RELAP5 code, and two traditional coordination control schemes were used to study the system operation characteristics under load drop transient condition. Each key system parameter response characteristics was investigated. Finally, based on the research results, an optimized operation scheme that was proved to have better system control effect was proposed.

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“…In CO 2 supercritical Brayton cycle, CO 2 releasing heat energy at supercritical state, which differs from CO 2 transcritical power cycle. Batet et al [16] established a model for CO 2 power cycle in using nuclear power and analyzed the performance in stable condition and variable condition. Garg et al [17] compared the performance between CO 2 transcritical power cycle and steam transcritical power cycle.…”

Section: Introductionmentioning

confidence: 99%

Experimental investigation on the CO 2 transcritical power cycle

Pan

Wei

et al. 2016

Energy

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Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5–3D

Cited by 17 publications

References 8 publications

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO₂ heat removal system coupled to a pressurized water reactor

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO₂ heat removal system coupled to a pressurized water reactor

Operation characteristic of supercritical carbon dioxide-cooled reactor system under coordination control scheme

Experimental investigation on the CO 2 transcritical power cycle

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Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5–3D

Cited by 17 publications

References 8 publications

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO2 heat removal system coupled to a pressurized water reactor

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO2 heat removal system coupled to a pressurized water reactor

Operation characteristic of supercritical carbon dioxide-cooled reactor system under coordination control scheme

Experimental investigation on the CO 2 transcritical power cycle

Contact Info

Product

Resources

About

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO₂ heat removal system coupled to a pressurized water reactor

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO₂ heat removal system coupled to a pressurized water reactor