Design Features and Simulation of the New-Build HELOKA-US Facility for the Validation of the DEMO Helium-Cooled Pebble Bed Intermediate Heat Transport and Storage System

Autor: Xiaoyang Gaus-Liu, Evaldas Bubelis, Sara Perez-Martin, Bradut-Eugen Ghidersa, Wolfgang Hering

Publikováno v: Journal of Nuclear Engineering, Vol 3, Iss 4, Pp 461-472 (2022)

For the EU-DEMO Helium-Cooled Pebble Bed (HCPB) concept, an indirect coupled design (ICD) with a molten salt (MS) loop as an intermediate heat transport and storage system (IHTS) is considered for the conceptual design phase. The IHTS with an energy

Externí odkaz: https://doaj.org/article/82e9fb2d60824851ba11f566b3751c0b

R&D Needs for the Design of the EU-DEMO HCPB ICD Balance of Plant in FP9

Autor: Barucca, Sara Perez-Martin, Evaldas Bubelis, Wolfgang Hering, Luciana

Publikováno v: Journal of Nuclear Engineering; Volume 3; Issue 4; Pages: 435-445

During the Pre-Conceptual Design Phase of the EU-DEMO, two BOP solutions for WCLL and HCPB were elaborated, as close as possible to industrial standards. Nevertheless, each solution has open issues to be investigated, analytically and experimentally,

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=multidiscipl::6d808073d427d84451a7f9c15a838603

A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

Autor: Sara Perez-Martin, Christophe Peniguel, Antoine Gerschenfeld, Laurent Laborde, Stephane Mimouni, Konstantin Mikityuk, Haileyesus Tsige-Tamirat, Werner Pfrang, Marine Anderhuber

Publikováno v: Journal of Nuclear Engineering and Radiation Science
Journal of Nuclear Engineering and Radiation Science, 2021, 8 (1), ⟨10.1115/1.4051066⟩

International audience; The Euratom Horizon-2020 project European sodium fast reactor safety measures assessment and research tools (ESFR-SMART) aims to enhance the safety and performance of the European sodium-cooled fast reactor (ESFR) considering

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7526df0b6b7ba25624e7b9628f778b2e

Evaluation of sodium boiling models using KNS-37 LOF experiments

Autor: Sara Perez-Martin, Laurent Laborde, Calogera Lombardo, N. Girault, Marine Anderhuber, Werner Pfrang, Christophe Peniguel, Luca Ammirabile, Konstantin Mikityuk, Stephane Mimouni

Publikováno v: Journal of Nuclear Engineering and Radiation Science

The computational codes used in the evaluation of the ESFR-SMART reactor performance and specifically their sodium boiling models are assessed using two KNS-37 LOF experiments, i.e. L22 and L29 tests, where boiling onset and two-phase flow regime up

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c93e0ab83397cad04ef6dd9251771721
https://doi.org/10.1115/1.4050769

ASTEC-Na code: Thermal-hydraulic model validation and benchmarking with other codes

Autor: V. Matuzas, M. Haselbauer, S. Ederli, Laurent Laborde, Luis E. Herranz, A. Flores y Flores, Sara Perez-Martin, C. Berna, N. Girault, Giacomino Bandini, Werner Pfrang

Publikováno v: Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2018, 119, pp.427-439. ⟨10.1016/j.anucene.2017.12.016⟩

International audience; This paper describes the work performed within the WP2.1 of the JASMIN project to validate the thermal-hydraulic models of ASTEC-Na code. The experiments used for validation purposes have been BI1, E8 and EFM1, carried out in

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a14f32c36866b28d9d2248311c800f13
https://doi.org/10.1016/j.anucene.2017.12.016