Abstract:Summary
In this paper, development and preliminary validation of an in‐house code LETHAC (lead‐based fast reactor thermal‐hydraulic analysis code) is introduced. LETHAC is developed for predicting the thermal‐hydraulic transient performance of a lead‐bismuth reactor. The mathematical models and module relations of LETHAC are presented in detail. The most‐used LBE (lead‐bismuth eutectic) flow and heat transfer correlations are compared against data from KYLIN‐II 61‐rod wire‐wrapped bundle experiments. Results s… Show more
“…The thermal-hydraulic code for transient assessment of lead and LBE reactors was developed and validated [ 58 ]. The developed code LETHAC was utilized and the results were compared to information from the KYLIN-II experiment having a 61-fuel pin bundle.…”
Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning
“…The thermal-hydraulic code for transient assessment of lead and LBE reactors was developed and validated [ 58 ]. The developed code LETHAC was utilized and the results were compared to information from the KYLIN-II experiment having a 61-fuel pin bundle.…”
Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning
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