NEA RBHT - Rod Bundle Heat Transfer

• Forschungsstelle: ENSI
• Projektnummer: CTR00614

Schlüsselwörter (Englisch)

Fuel Element; Loss of Coolant Accident LOCA; Reflooding; Heat Transfer

Kurzbeschreibung (Englisch)

The objective of this three-year activity is to conduct new experiments and evaluate system hydraulics and sub-channel codes in the simulation of reflood tests in a full height rod bundle for complex inlet flows. While numerous experimental tests have been conducted for steady, constant inlet conditions, relatively few experiments have examined variable or oscillating inlet flows which are more likely in a hypothetical accident scenario. This benchmark exercise will produce and provide to participants a set of reflood test data with variable, oscillatory as well as constant reflood inlet flows. Numerical simulations of an initial set of data will be performed to examine code capability, and then “blind” simulations of similar conditions performed prior to release of the experimental data. In the so-called “blind” tests, the as measured initial and boundary conditions are provided to participants who then attempt to predict the test results. Results are then made available so that they can be compared to the simulations. A quantification of code uncertainty as part of prediction of the “blind” data will be part of the exercise.

Projektziele (Englisch)

Existing reflood experiments had demonstrated the effectiveness of the Emergency Core Cooling System, and a reflood facility with advanced and detailed measurement capabilities have been considered an important next stage. The proposed project is aimed at improving on the accuracy of thermal-hydraulic codes used in the analysis and licensing of nuclear reactors. The activity will produce new and unique experimental data for code assessment and provide an opportunity for participants to quantify code accuracy.