Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Advanced High Temperature Reactor (SmAHTR)

Greene, S.R.; Gehin, Jess C; Holcomb, David Eugene; Carbajo, J.J.; Ilas, Dan; Cisneros, Anselmo T.; Varma, Venugopal Koikal; Corwin, W.R.; Wilson, Daniel A.; Yoder, G.L.; Qualls, A. L.; Peretz, F.J.; Flanagan, G.F.; Clayton, Dwight A; Bradley, Eric; Bell, Gary; Hunn, John D.; Pappano, Peter J; Cetiner, Mustafa Sacit

doi:10.2172/1008830

Cited by 64 publications

(42 citation statements)

References 14 publications

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“…A small FHR pin-type fuel assembly design is taken from the SmAHTR study [9][13] as shown in Figure 1. The fuel assembly design with 19.75 wt.% UO 2 fuels is run with a 172-group calculation in WIMS with the JEF-2.2, JEFF-3.1 and ENDF/B-VII data libraries.…”

Section: Methodsmentioning

confidence: 99%

“…Majority of reviewed fluoride salt-cooled high-temperature reactor (FHR) studies, including the Small modular Advanced High-Temperature Reactor (SmAHTR) pre-conceptual report [9], do not provide sufficient details on the data libraries used in their analyses. Only few of them clearly explain the data libraries used such as Ingersoll et al [10], Clarno et al [11] and Szakaly et al [12] in their Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) studies.…”

Section: Introductionmentioning

confidence: 99%

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Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor

Mohamed

Lindley

Parks

2017

AIP Conference Proceedings

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Abstract. Nuclear data consists of measured or evaluated probabilities of various fundamental physical interactions involving the nuclei of atoms and their properties. Most fluoride salt-cooled high-temperature reactor (FHR) studies that were reviewed do not give detailed information on the data libraries used in their assessments. Therefore, the main objective of this data libraries comparison study is to investigate whether there are any significant discrepancies between main data libraries, namely ENDF/B-VII, JEFF-3.1 and JEF-2.2. Knowing the discrepancies, especially its magnitude, is important and relevant for readers as to whether further cautions are necessary for any future verification or validation processes when modelling an FHR. The study is performed using AMEC's reactor physics software tool, WIMS. The WIMS calculation is simply a 2-D infinite lattice of fuel assembly calculation. The comparison between the data libraries in terms of infinite multiplication factor, k inf and pin power map are presented. Results show that the discrepancy between JEFF-3.1 and ENDF/B-VII libraries is reasonably small but increases as the fuel depletes due to the data libraries uncertainties that are accumulated at each burnup step. Additionally, there are large discrepancies between JEF-2.2 and ENDF/B-VII because of the inadequacy of the JEF-2.2 library.

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor

Mohamed

Lindley

Parks

2017

AIP Conference Proceedings

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“…Thermal-hydraulic analysis of crossflow PCHE was carried out based on the values in Tables 3 and 4. [38] Na/Na 545/390 320/526 0.1/0.1 Molten Salt-cooled [39] FLiBe/FLiNaK 700/650 600/690 0.1/0.1…”

Section: Thermal-hydraulic Analysis Of Crossflow Pchementioning

confidence: 99%

Analytical Study on Thermal and Mechanical Design of Printed Circuit Heat Exchanger

Yoon

Sabharwall

Kim

2013

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The analytical methodologies for the thermal design, mechanical design, and cost estimation of printed circuit heat exchanger are presented in this study. Three flow arrangements for PCHE of parallel flow, countercurrent flow and crossflow are taken into account. For each flow arrangement, the analytical solution of temperature profile of heat exchanger is introduced. The size and cost of printed circuit heat exchangers for advanced small modular reactors are also presented using various coolants such as sodium, molten salts, helium, and water. viii ix SUMMARYPrinted Circuit Heat Exchanger (PCHE) is one of the candidate designs of Very High Temperature Reactor (VHTR) or Advanced High Temperature Reactor (AHTR) heat exchanger (HX). Fine grooves in the plate of PCHE are made by using the technique that is employed for making printed circuit board. This heat exchanger is formed by the diffusion bonding of stacked plates whose grooved surfaces are the flow paths. Thermal design of heat exchanger is required to determine the size and effectiveness of heat exchanger. To evaluate the structural integrity, mechanical design of heat exchanger must be investigated. In a previous study, the parallel/counter flow PCHE analysis code was developed. The methodologies for the thermal and mechanical design of parallel/counter flow PCHE used in previous study are also summarized in this report.The objective of this work is to develop the analysis code for the crossflow PCHE to determine the size and cost of crossflow PCHE for AHTR. The size of the crossflow PCHE is determined through thermal design process of heat exchanger. Two dimensional temperature profiles in primary and secondary sides of crossflow PCHE are obtained from the solution of analytical model of crossflow PCHE assuming a single pass, both with unmixed fluid, and no contribution from longitudinal heat conduction. The mechanical design of crossflow PCHE is to determine the criteria of geometric parameters of structure for maintaining the integrity of the heat exchanger. The method for mechanical design of crossflow PCHE is developed based on that of parallel/counter flow PCHE.To verify the developed code, the grid sensitivity test and effectiveness-number of transfer units (NTU) analysis were carried out. The grid sensitivity test for the developed code was performed to evaluate the effect of grid number on the result. The result of grid sensitivity test shows that the effect of grid number is negligible. The effectiveness-NTU analysis was carried out to verify the developed code. The calculated effectiveness by the code and -NTU correlation for crossflow heat exchanger shows a good agreement with each other.As a parametric study, uncertainty analyses for fluid properties and heat transfer correlation were performed. The uncertainty of fluid properties was investigated by assuming ±30% of uncertainty in fluid material properties. The result of uncertainty analysis shows that the uncertainty of fluid property was negligible in the thermal design of crossflow...

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“…Road (16) and rail access (17) to the site is seen to the left. The main parking lot, adjacent to the administration building, is within the property protection area.…”

Section: Fig 7 Overall Plant Layoutmentioning

confidence: 99%

“…17 Within the slab fuel element, the TRISO fuel particles are distributed in two stripes separated by central carbonaceous material. This represents the main departure from the SmAHTR fuel, where the fuel was distributed throughout the plate.…”

Section: Fuel Platementioning

confidence: 99%

AHTR Mechanical, Structural, and Neutronic Preconceptual Design

Varma¹,

Holcomb²,

Peretz³

et al. 2012

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Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Advanced High Temperature Reactor (SmAHTR)

Cited by 64 publications

References 14 publications

Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor

Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor

Analytical Study on Thermal and Mechanical Design of Printed Circuit Heat Exchanger

AHTR Mechanical, Structural, and Neutronic Preconceptual Design

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