journal article·2020-10-21Open access

Numerical Analysis of the CIRCE-HERO PLOFA Scenarios

Moscardini Marigrazia, Galleni Francesco, Pucciarelli Andrea, Martelli Daniele, Forgione Nicola

Applied Sciences· Volume 10· Issue 20

Abstract

The present work deals with simulations carried out at the University of Pisa by using the System Thermal Hydraulics code RELAP5/Mod3.3 to support the experimental campaign conducted at the ENEA (Energia Nucleare ed Energie Alternative) Brasimone Research Centre on the CIRColazione Eutettico—Heavy liquid mEtal pRessurized water cOoled tubes (CIRCE-HERO) facility. CIRCE is an integral effect pool type facility dedicated to the study of innovative nuclear systems and cooled by heavy liquid metal, while HERO is a heat exchanger heavy liquid metal/ pressurized cooling water system hosted inside the CIRCE facility. Beside the H2020 project Multi-Purpose Hybrid Research Reactor for High-Tech Applications (MYRRHA) Research and Transmutation Endeavour (MYRTE), a series of experiments were performed with the CIRCE-HERO facility, for both nominal steady-state settings and accidental scenarios. In this framework, the RELAP5/Mod3.3 code was used to simulate the experimental tests assessing the heat losses of the facility and analyzing the thermal hydraulics phenomena occurring during the postulated Protected Loss Of Flow Accident (PLOFA). The modified version Mod. 3.3 of the source code RELAP5 was developed by the University of Pisa to include the updated thermo–physical properties and convective heat transfer correlations suitable for heavy liquid metals. After reproducing the facility through an accurate nodalization, boundary conditions were applied according to the experiments. Then, the PLOFA scenarios were reproduced by implementing the information obtained by the experimental campaign. Sensitivity analyses of the main parameters affecting the thermofluidynamics of the Lead-Bismuth Eutectic (LBE) were carried out. In the simulated scenario, the LBE mass flow rate strongly depends on the injected argon flow time trend. The numerical results are in agreement with the experimental data, however further investigations are planned to analyze the complex phenomena involved.
Source: crossref · Quality: baseline

Research context

OpenAlex topics: Nuclear reactor physics and engineering · Nuclear Materials and Properties · Nuclear Engineering Thermal-Hydraulics

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

Affiliations

Department of Civil and Industrial Engineering, University of Pisa, 56122 Pisa, Italy

ENEA, FSN-ING, Brasimone Research Centre, 40032 Camugnano (Bo), Italy

Funding

H2020 Euratom

References (19)

Show source-provided references
1. Baudrand, O., Blanc, D., Bourgois, T., Ivanov, E., Bonneville, H., Bruna, G., Clément, B., Hache, G., Kissane, M., and Meignen, R. (2012). Overview of Generation IV (Gen IV) Reactor Designs-Safety and Radiological Protection Considerations, Institut de Radioprotection et de Surete Nucleaire-IRSN. IRSN Rep. 2012/158.
2. Roelofs, F. (2019). Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors, Elsevier. Woodhead Publishing.10.1016/B978-0-08-101980-1.00001-6 ↗
3. Overview of lead-cooled fast reactor activities10.1016/j.pnucene.2013.11.011 ↗
4. (2020, October 13). “GIF 2019 Annual Report”, Generation IV International Forum. Available online: https://www.gen-4.org/gif/jcms/c_119034/gif-2019-annual-report.
5. Fletcher, C.D., and Schultz, R.R. (2001). RELAP5/Mod3.3 Code Manual Volume I: Code Structure, System Models, and Solution Methods, Information Systems Laboratories, Inc.. Nuclear Safety Analysis Division.
6. Fletcher, C.D., and Schultz, R.R. (2001). RELAP5/Mod3.3 Code Manual Volume V: User’s Guidelines, Information Systems Laboratories, Inc.. Nuclear Safety Analysis Division.
7. Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility10.1016/j.nucengdes.2019.110169 ↗
8. MYRRHA primary heat exchanger experimental simulations on CIRCE-HERO10.1016/j.nucengdes.2019.110270 ↗
9. Roelofs, F. (2019). System thermal hydraulics for liquid metals. Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors, Woodhead Publishing.10.1016/B978-0-08-101980-1.00001-6 ↗
10. Sobolev, V. (2011). Database of Thermophysical Properties of Liquid Metal Coolants for GEN-IV, Centre D’etude de L’energie Nucléaire. (rev. December 2011).
11. Heat transfer to liquid metals in regular arrays of fuel elements TVT
12. Heat transfer to a fluid flowing turbulently in a smooth pipe with walls at constant temperature10.1115/1.4016437 ↗
13. Implementation of Lead-Lithium as working fluid in RELAP5/Mod3.310.1016/j.fusengdes.2019.02.064 ↗
14. Application of RELAP5/Mod3.3-Fluent coupling codes to CIRCE-HERO10.1088/1742-6596/1224/1/012032 ↗
15. Post-test simulations for the NACIE-UP benchmark by STH codes10.1016/j.nucengdes.2019.110279 ↗
16. Forgione, N., Angelucci, M., Barone, G., Polidori, M., Cervone, A., di Piazza, I., Giannetti, F., Lorusso, P., Hollands, T., and Papukchiev, A. (2018, January 22–26). Blind simulations of NACIE-UP experimental tests by STH codes. Proceedings of the International Conference on Nuclear Engineering, ICONE, 4, ASME, London, UK.10.1115/ICONE26-81434 ↗
17. Gonfiotti, B., Barone, G., Angelucci, M., Martelli, D., Forgione, N., del Nevo, A., and Tarantino, M. (2018, January 22–26). Thermal hydraulic analysis of the circe-hero pool-type facility. Proceedings of the International Conference on Nuclear Engineering, ICONE, 6B, ASME, London, UK.10.1115/ICONE26-82589 ↗
18. Analysis of the thermal stratification phenomena in the CIRCE-HERO facility10.1016/j.anucene.2020.107320 ↗
19. Pucciarelli, A., Galleni, F., Moscardini, M., Martelli, D., and Forgione, N. (2020). STH/CFD coupled simulation of the protected loss of flow accident in the CIRCE-HERO facility. Appl. Sci., 10.10.3390/app10207032 ↗