AREVA HTR concept for near-term deployment

Lommers, Lewis; Shahrokhi, F.; Mayer, J.; Southworth, Frank

doi:10.1016/j.nucengdes.2011.10.030

Cited by 19 publications

(12 citation statements)

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“…It results in extensive "piling-up" temperature in steam generator that additionally improves heat exchange parameters and allows to decrease dimensions of the generator. Moreover, water present in steam cycle is not subjected to radioactive exposure [16,19] .…”

Section: Htr Reactorsmentioning

confidence: 99%

“…Special attention should be paid to HTR nuclear reactors. This is a prospective , fast developing solution both for power industry and sea transport [4,16,19,21]. This work is aimed at making analysis of possible profits, in thermodynamic and operational aspects, resulting from application of HTR reactors into ship nuclear power plants of a large output with taking into account load variability , in particular.…”

Section: Introductionmentioning

confidence: 99%

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Analysis of Possible Application of High-Temperature Nuclear Reactors to Contemporary Large-Output Steam Power Plants on Ships

Kowalczyk

Głuch

Ziółkowski

2016

Polish Maritime Research

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Section: Htr Reactorsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Analysis of Possible Application of High-Temperature Nuclear Reactors to Contemporary Large-Output Steam Power Plants on Ships

Kowalczyk

Głuch

Ziółkowski

2016

Polish Maritime Research

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“…Based on prior design data for prismatic cores, this would correspond to a maximum ROT of ~770°C. The recent recommendations by General Atomics 13 and AREVA 14 for the initial deployment of the HTGR technology employ ROTs below this value, providing confidence that SA508/533 material can be used for the RPVs in these designs.…”

Section: Fig 16 Maximum Temperatures Of the Rpv According To A Changmentioning

confidence: 99%

Using SA508/533 for the HTGR Vessel Material

Demick¹

2012

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This paper examines the influence of high temperature gas-cooled reactor module power rating and normal operating temperatures on the viability of using SA508/533 material for the high temperature gas-cooled reactor vessel system with emphasis on the calculated times at elevated temperatures approaching or exceeding American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III Service Limits (Levels A, B, and C) to which the reactor pressure vessel could be exposed during normal operation and postulated pressurized and depressurized conduction cooldown events over its design lifetime.

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“…Buoyancy induced by natural convection phenomenon with smooth and rough walls has been a subject of many research studies for decades being rich in its applications [1]. Its significance is further enhanced because of its incorporation in passive safety systems of Small Modular Reactors (SMRs) and advanced generations of nuclear reactors [2]. It has remarkable applications from micro scale to macro scale devices, and especially in nuclear industry like removal of decay heat during accident and shutdown phases, nuclear reactor design and safety, reactor insulation, design of radioactive waste containers etc.…”

Section: Introductionmentioning

confidence: 99%

Role of Surface Roughness during Natural Convection

Rolla¹,

Mo²

2015

WJET

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A computational study was performed in a two-dimensional square cavity in the presence of roughness using an algorithm based on mesoscopic method known as Lattice Boltzmann Method (LBM). A single relaxation time Bhatnagar-Gross-Krook (BGK) model of LBM was used to perform numerical study. Sinusoidal roughness elements of dimensionless amplitude of 0.1 were located on both the hot and cold walls of a square cavity. A Newtonian fluid of the Prandtl number (Pr) 1.0 was considered. The range of the Rayleigh (Ra) number explored was from 10 3 to 10 6 in a laminar region. Thermal and hydrodynamic behaviors of fluid were studied using sinusoidal roughness elements. Validation of computational algorithm was performed against previous benchmark studies, and a good agreement was found. Average Nu (Nusselt number) has been calculated to observe the effects of the surface roughness on the heat transfer. Results showed that sinusoidal roughness elements considerably affect the thermal and hydrodynamic behaviors of fluid in a square cavity. The maximum reduction in the average heat transfer in the presence of roughness was calculated to be 23.33%.

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AREVA HTR concept for near-term deployment

Cited by 19 publications

References 0 publications

Analysis of Possible Application of High-Temperature Nuclear Reactors to Contemporary Large-Output Steam Power Plants on Ships

Analysis of Possible Application of High-Temperature Nuclear Reactors to Contemporary Large-Output Steam Power Plants on Ships

Using SA508/533 for the HTGR Vessel Material

Role of Surface Roughness during Natural Convection

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