NGNP Point Design - Results of the Initial Neutronics and Thermal-Hydraulic Assessments During FY-03, Rev. 1

MacDonald, P.E.; Sterbentz, James W.; Sant, R. L.; Bayless, Paul D.; Gougar, Hans D.; Moore, Richard L.; Ougouag, Abderrafi M.; Terry, William S.

doi:10.2172/910732

Cited by 31 publications

(2 citation statements)

References 16 publications

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“…This distribution was generated using Monte Carlo code MCNP4C or a 10-ring core model. The axial power profile chosen is based on a profile used by ORNL to model the LS-VHTR [2,9] and is shown in Fig 6 . Both radial and axial normalized power factors (called multiplication factors) are specified for each axial segment in the heat structures that are coupled to the thermal hydraulic channels that shape the reactor core. The normalization is performed according to the number of THC simulated in the case of radial power factors, and normalized according to the number of axial meshes, and in the case of axial power factors.…”

Section: Methodsmentioning

confidence: 99%

Thermal-hydraulic modelling and stade staty analysis of a LS-VHTR reactor

Ramos,

Costa,

Veloso

et al. 2023

Braz. J. Develop.

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The Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) is a liquid salt cooled and TRISO fueled reactor, which presents very good features in terms of power production and safety aspects. The advantage of using liquid salt as coolant is mainly related with its high efficiency of heat transfer and operation at low pressures. This work evaluates the thermal hydraulic performance of the heat removal system and the reactor core, in steady state conditions, starting from the single channel level and concluding with the full core model. The LS-VHTR is a new reactor concept that introduces some different features in relation to other nuclear reactors. In this way, a thermal modeling of this reactor has been developed using the RELAP5-3D code using a point kinetic model. A modeling with three channels has been presented. The core coolant temperature increase, the core coolant mass flow and the pressure along the core were simulated and presented in good agreement with the expected behavior

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Section: Methodsmentioning

confidence: 99%

Thermal-hydraulic modelling and stade staty analysis of a LS-VHTR reactor

Ramos,

Costa,

Veloso

et al. 2023

Braz. J. Develop.

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“…Among the existing proposals for nuclear power in space, the gas-cooled reactor plus closed Brayton cycle is the most promising technological solution with high efficiency and stability [4][5][6]. Currently, the main concept design of the ultra-high temperature gas-cooled reactor is helium, whose reactor outlet temperature reaches about 1240 K [7]. However, the size of presently designed helium turbines is too large for space missions with strict size constraints [8].…”

Section: Introductionmentioning

confidence: 99%

Comprehensive Thermodynamic Analysis of He–Xe in Microchannels with Different Structures

et al. 2023

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He–Xe, with a 40 g/mol molar mass, is considered one of the most promising working media in a space-confined Brayton cycle. The thermodynamic performance of He–Xe in different configuration channels is investigated in this paper to provide a basis for the optimal design of printed circuit board plate heat exchanger (PCHE). In this paper, the factors affecting the temperature distribution of the He–Xe flow field are analyzed based on the flow heat transfer mechanism. It is found that the flow patterns in the logarithmic and outer zones determine the temperature distribution pattern of the flow field. A series of numerical simulations verify the above conclusions, and it is found that reasonable channel structure and operating conditions can significantly improve the thermodynamic performance of the He–Xe flow. Based on the above findings, the Zig channel is optimized, obtaining Sine and Serpentine channels with different structural characteristics. Comprehensive thermodynamic comparisons of the helium–xenon flow domains inside channels are performed, and the Serpentine channel with a shape factor of tan 52.5° is found with the best performance. This work aims to improve the understanding of the thermodynamic performance of He–Xe in microchannels and provide theoretical support for further optimization of PCHE employing He–Xe.

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Stochastic geometry capability in MCNP5 for the analysis of particle fuel

Brown

Martin

2004

Annals of Nuclear Energy

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NGNP Point Design - Results of the Initial Neutronics and Thermal-Hydraulic Assessments During FY-03, Rev. 1

Cited by 31 publications

References 16 publications

Thermal-hydraulic modelling and stade staty analysis of a LS-VHTR reactor

Thermal-hydraulic modelling and stade staty analysis of a LS-VHTR reactor

Comprehensive Thermodynamic Analysis of He–Xe in Microchannels with Different Structures

Stochastic geometry capability in MCNP5 for the analysis of particle fuel

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