Investigation on RELAP5-3D© capability to predict thermal stratification in liquid metal pool-type system and comparison with experimental data
- 1. DIAEE – Nuclear Section, "Sapienza" University of Rome, Corso Vittorio Emanuele II, 244, 00186 Rome (Italy)
Description
Highlights: • Thermal-hydraulic transient analysis for a LBE pool-type facility. • Investigation of RELAP5-3D capability to reproduce the transition from forced to natural circulation in a HLM pool system. • Verification of RELAP5-3D capability to reproduce the main thermal-hydraulic phenomena in a large HLM pool. • Comparison between the computational results and the experimental data. - Abstract: A numerical activity, aimed to evaluate the capability of RELAP5-3D© to reproduce the main thermal-hydraulic phenomena in an HLM pool-type facility, in different operative conditions, is presented. For this purpose, the experimental campaign performed in CIRCE-ICE test facility has been selected for the code assessment. Two experimental tests have been analyzed: TEST A consisting in a transition from no-power to a full power steady state conditions, and TEST I, consisting in a transition from gas-enhanced circulation to natural circulation, simulating a protected loss of heat sink plus a loss of flow accident. Three different pool modelling approaches are presented, consisting in a single vertical pipe, parallel pipes with cross junctions and multi-dimensional component. The comparison with experimental data has highlighted the need to divide the large pool in several sections to reproduce the natural convection, strictly correlated with the thermal stratification. The multi-dimensional component seems to be the best practice for the evaluation of this phenomenon even if the lack of specific correlation for heat transfer coefficient in quasi-stagnant conditions in large tanks is a limit for the accuracy of the results. In addition, the paper presents a detailed nodalization of the fuel pin bundle, highlighting quite good capabilities of RELAP5-3D as a subchannel analysis code.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2019.110152Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2019.110152;
- PII
- S0029549319301633;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 352
- Journal Page Range
- p. 110152
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51056271
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- FUEL PINS; LIQUID METALS; LOSS OF FLOW; NATURAL CONVECTION; PONDS; SAFETY ANALYSIS; STEADY-STATE CONDITIONS; STRATIFICATION; TEST FACILITIES; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CONVECTION; ELEMENTS; ENERGY TRANSFER; FLUID MECHANICS; FLUIDS; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; LIQUIDS; MASS TRANSFER; MECHANICS; METALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; SURFACE WATERS
Optional Information
- Notes
- © 2019 Elsevier B.V. All rights reserved.