Validation of the Hybrid Turbulence Model in Detailed Thermal-Hydraulic Analysis Code SPIRAL for Fuel Assembly Using Sodium Experiments Data of 37-Pin Bundles

• Published in: Nuclear technology 2024-05, Vol.210 (5), p.814-835
• Main Authors: Yoshikawa, Ryuji, Imai, Yasutomo, Kikuchi, Norihiro, Tanaka, Masaaki, Ohshima, Hiroyuki
• Format: Article
• Language: English
• Subjects: fuel assembly; Hydraulics; Sodium; Sodium-cooled fast reactor; thermal hydraulics; Turbulence models; wire-wrapped pin bundle
• ISSN: 0029-5450; 1943-7471
• DOI: 10.1080/00295450.2023.2249707

In the study of safety enhancements on advanced sodium-cooled fast reactors (SFRs) by the Japan Atomic Energy Agency (JAEA), it has been essential to clarify the thermal hydraulics under various operating conditions at high and low flow rate conditions in a fuel assembly (FA) with wire-wrapped fuel pins to assess the structural integrity of the fuel pin that achieves a high-performance core with high burnup ratio and high power density. A finite element thermal-hydraulic analysis code named SPIRAL has been developed by JAEA to analyze the detailed thermal-hydraulic phenomena in the FA of a SFR. In this study, numerical simulations of 37-pin bundle sodium experiments at different Reynolds (Re) number conditions, including a transitional condition between laminar and turbulent flows and turbulent flow conditions, were performed to validate the developed hybrid k-ε/k θ -ε θ turbulence model equipped in SPIRAL to consider the low Re number effect near the wall in the flow and temperature fields. The temperature distributions predicted by SPIRAL were consistent with those measured in the sodium experiments at the Re number conditions. Through the validation study, the applicability of the hybrid turbulence model in SPIRAL to the thermal-hydraulic evaluation of sodium-cooled FAs in a wide range of Re numbers was confirmed.