Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies
Fluorine compounds; High temperature reactors; Sensitivity analysis; Coolant temperature; Discharge burn-up; External coupling; Fuel assembly design; High temperature; Reactor physics; Thermal hydraulics; Thermal-hydraulic analysis; Fuels
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American Nuclear Society
2023
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my.uniten.dspace-229362023-05-29T14:13:31Z Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies Mohamed H. Kotlyar D. Parks G. Shaposhnik Y. 57136356100 45661217600 7103057721 51261305700 Fluorine compounds; High temperature reactors; Sensitivity analysis; Coolant temperature; Discharge burn-up; External coupling; Fuel assembly design; High temperature; Reactor physics; Thermal hydraulics; Thermal-hydraulic analysis; Fuels This study undertook a coupled neutronic-thermal-hydraulic analysis of a small fluoride salt-cooled high-temperature reactor (FHR), one of the advanced Gen. IV concepts. The objective is to further investigate the practical feasibility of two UO2 pin-type fuel assembly designs, namely 3- and 4-ring designs, by looking primarily at thermal-hydraulic (TH) parameters, such as linear power and fuel centreline temperature, as well as radial power peaking. The coupled neutronic-TH analysis was performed by the external coupling of Serpent, a Monte Carlo based reactor physics code, with the TH feedback provided by THERMO. Sensitivity analysis was performed by varying the fuel pin radius by �5% and �10% of its original size. Results show that the 4-ring design has better TH performance than the 3-ring design. However, this TH advantage is outweighed by the superior ncutronic performance offered by the 3-ring design. The change in fuel pin radius docs not significantly affect fuel centreline and coolant temperatures for either design, but the discharge burnup and pressure drop increase with increasing fuel pin radius. Final 2023-05-29T06:13:31Z 2023-05-29T06:13:31Z 2016 Conference Paper 2-s2.0-84992123224 https://www.scopus.com/inward/record.uri?eid=2-s2.0-84992123224&partnerID=40&md5=88f8270d62c6304d50f659162eec764b https://irepository.uniten.edu.my/handle/123456789/22936 4 2630 2639 American Nuclear Society Scopus |
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| description |
Fluorine compounds; High temperature reactors; Sensitivity analysis; Coolant temperature; Discharge burn-up; External coupling; Fuel assembly design; High temperature; Reactor physics; Thermal hydraulics; Thermal-hydraulic analysis; Fuels |
| author2 |
57136356100 |
| author_facet |
57136356100 Mohamed H. Kotlyar D. Parks G. Shaposhnik Y. |
| format |
Conference Paper |
| author |
Mohamed H. Kotlyar D. Parks G. Shaposhnik Y. |
| spellingShingle |
Mohamed H. Kotlyar D. Parks G. Shaposhnik Y. Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies |
| author_sort |
Mohamed H. |
| title |
Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies |
| title_short |
Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies |
| title_full |
Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies |
| title_fullStr |
Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies |
| title_full_unstemmed |
Coupled neutronic-thermal-hydraulic analysis of a small FHR core with pin-type fuel assemblies |
| title_sort |
coupled neutronic-thermal-hydraulic analysis of a small fhr core with pin-type fuel assemblies |
| publisher |
American Nuclear Society |
| publishDate |
2023 |
| _version_ |
1806425772789858304 |
| score |
13.214268 |