{"id":19661,"date":"2025-07-03T18:22:56","date_gmt":"2025-07-03T16:22:56","guid":{"rendered":"https:\/\/www.crs4.it\/projects\/search\/"},"modified":"2026-04-02T12:36:43","modified_gmt":"2026-04-02T10:36:43","slug":"search","status":"publish","type":"projects","link":"https:\/\/www.crs4.it\/en\/projects\/search\/","title":{"rendered":"SEARCH"},"content":{"rendered":"<p>The goal of the <strong>SEARCH<\/strong> proposal is to group critical safety related research focussed on the  coolability of the fuel with and without forced convection, the chemical  behaviour of the heavy liquid metal reactor coolant and impurities, the  interaction of fuel with the coolant and the behaviour of (volatile)  radioisotopes in the coolant. Indeed, although information of this type  is essential for the licencing process, it turns out that actual  experimental data in this field are rather scarce or non-existent.<br \/>\nThe scope of <strong>SEARCH<\/strong> encompasses basic studies  including an experimental and numerical analyses of heat transfer in the  fuel bundle, the determination of the impurities source terms, the  investigation of migration, deposition and release of impurities and  radioisotopes and finally the development of capture and purification  techniques. In particular the objectives of the project are to:<\/p>\n<ul>\n<li>Study the heat transfer of a wire spaced fuel bundle in forced and natural convection <\/li>\n<li>Investigate the source term for impurities in the coolant  including corrosion products, spallation and activation materials and  water from a possible heat exchanger leakage.<\/li>\n<li>Study the mass-transport of dissolved metals and oxides in the coolant.<\/li>\n<li>Develop filtering techniques for the coolant in both loop and pool configuration.<\/li>\n<li>Develop and validate an oxygen control system based on solid  oxide particles including the influence of the cover gas, formation and  dissolution kinetics and measurement techniques in a deep pool  configuration. <\/li>\n<li>Study coolant-fuel interaction and characterise reaction products with their influence on fuel.<\/li>\n<li>Study the phase relations of the elements in MOX fuel and the coolant (Pb-U-O, Bi-U-O, Pb-Pu-O, Bi-Pu-O).<\/li>\n<li>Investigate the dispersion of fuel through the reactor system in  case of a core melt and in case of slow fuel release by computational  fluid dynamics (CFD) and SIMMER simulations.<\/li>\n<li>Identify and study the parameters that influence the  evaporation, gas phase transport and deposition processes of  radioisotopes from the coolant including the chemical composition of the  evaporated compounds<\/li>\n<li>Determine physicochemical parameters necessary for the  prediction of vapour phase concentrations of radionuclides in an ADS and  the development of gas phase filtering systems for their removal. <\/li>\n<li>Use ab-initio quantum-mechanical calculations to calculate  crucial properties of the evaporation and deposition processes of  volatile radionuclide including the interaction with potential filter  materials.<\/li>\n<\/ul>\n<p>The main motivation for the selection of these specific topics is  that they all are related to important operational and safety issues.<br \/>\nThe coolability of the fuel is the most essential issue in the design  and operation of a nuclear system. Both in forced convection and in  natural convection which may occur after a loss of flow as happened in  de Fukushima accident coolability must be guaranteed. Another type of  failure of the cooling can happen because of an assembly or channel  blockage. In this respect the chemistry control of the coolant of a  heavy liquid metal cooled nuclear system in normal operation is very  important. The chemistry control concept for heavy liquid metal coolants  can be subdivided in two major aspects. The first aspect is the  specific control of the oxygen content in the coolant. This is required  to protect the structural materials in the reactor from corrosion on the  one hand and to avoid excessive precipitation of lead- and bismuth  oxides on the other hand. The second major aspect of chemistry control  deals with the management of impurities in the coolant. It is clear that  uncontrolled impurities can lead to depositions in the reactor causing  reduced cooling or blockages with potential disastrous consequences. The  main sources of impurities are lead oxide precipitation, corrosion  products but also radioactive elements originating from spallation and  neutron activation reactions.<br \/>\nThe compatibility of the fuel and the coolant is a critical issue in  the safety assessment of a nuclear system. Both low probability accident  scenarios involving a (partial) core melt and the high probability  event of a leaking fuel pin must be considered. The full analyses of  these scenarios using appropriately validated codes like e.g. Simmer III  require further experimental data on basic properties of the  interactions between the materials involved in scenarios mentioned  above.<br \/>\nFor licencing preparation it is important to investigate the  consequences of the reference severe accident scenarios. Although the  selection of the reference accident for MYRRHA is not clear at this  point, it will most likely involve damage to the fuel pins. In <strong>SEARCH<\/strong> two scenarios will be considered: slow, long term release of fuel  corresponding to a set of leaking fuel pins and a scenario involving a  large, short term release of fuel which corresponds to a partial or  complete core melt. We will investigate the dispersion of molten fuel in  the system by means of numerical simulations.<br \/>\nThe main concern of the safety authorities is the prevention of risks  to the general public, both in normal operation of a nuclear reactor as  well as in accident scenarios. The most important risk is the escape of  radioactive materials to the environment. This means that the release  of these elements, both from fission in the fuel and from the spallation  and activation reactions in the liquid metal of an ADS system must be  investigated. Furthermore, possible methods to capture these elements in  the covergas conditioning system and their kinetics and efficiency  should be examined. In comparison to water cooled thermal reactors, a  lead-bismuth cooled ADS system such as MYRRHA has, besides fission  gasses and light activation products, the additional presence of heavy  volatile elements such like Po and Hg. For this reason the main focus  will be put on these elements. The release of Po into the environment in  various accident scenarios involving damage to the confinement  structure will be assessed using the experimental data gained in the  project.<br \/>\nIn all experiments LBE is selected as the primary coolant and not  pure lead. The reason for this choice is twofold. Firstly, since MYRRHA  will be the first HLM cooled nuclear system to be deployed in Europe as  shown in the ESNII roadmap, <strong>SEARCH<\/strong> will put its  emphasis on LBE as it is the coolant used in MYRRHA. Secondly, because  LBE is chemically more complex than pure lead, experiments performed  using LBE can more readily be extrapolated to pure lead at the same  temperature range whereas the reverse is not the case. In this sense  using LBE is more generic than using pure lead.<br \/>\n<strong>SEARCH<\/strong> will also include a work-package on education  and training. The objective is to organise a number of workshops and  schools with the objective to educate and train students and PhD&#8217;s in  topics relevant to the project.<br \/>\n<strong>SEARCH<\/strong> will be linked to existing FP7 projects  related to Gen IV system development in general and to LFR\/ADS systems  in particular. These include CDT (<em>Central Design Team<\/em>), LEADER (<em>Lead-cooled European Advanced Demonstration Reactor<\/em>) and THINS (<em>Thermal-Hydraulics of Innovative Nuclear Systems). <\/em>SEARCH will partly build on results obtained in the FP6 project EUROTRANS (<em>European Research Programme for the Transmutation of High Level Nuclear Waste in ADS<\/em>).<\/p>\n<p>\u00a0<\/p>\n<p>\u00a9 2014, SCK\u2022CEN<\/p>\n","protected":false},"featured_media":3797,"template":"","meta":{"_acf_changed":false},"gruppo":[],"class_list":["post-19661","projects","type-projects","status-publish","has-post-thumbnail","hentry"],"acf":{"title":"Safe ExploitAtion Related CHemistry for HLM reactors ","acronym":"SEARCH","project_uuid":"619767dc-b567-1032-95fe-0030485a3848","start_date":"01\/11\/2011","end_date":"28\/04\/2015","funder":"EU FP7","partners":"\n<table style=\"width:100%; border-collapse: collapse;\">\n  <tr>\n    <th style=\"border: 1px solid #ddd; padding: 8px; background-color: #f2f2f2;\">Nome<\/th>\n    <th style=\"border: 1px solid #ddd; padding: 8px; background-color: #f2f2f2;\">Nazione<\/th>\n    <th style=\"border: 1px solid #ddd; padding: 8px; background-color: #f2f2f2;\">Ruolo<\/th>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"http:\/\/www.sckcen.be\" target=\"_blank\">STUDIECENTRUM VOOR KERNENERGIE<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Belgium<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Coordinator<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"http:\/\/www.enea.it\" target=\"_blank\">Agenzia Nazionale per le nuove tecnologie, l&#x27;energia e lo sviluppo economico sostenibile<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Italy<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"https:\/\/www.kit.edu\/english\/index.php\" target=\"_blank\">Karlsruher Institut fuer Technologie <\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Germany<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"http:\/\/www.nrg.eu\" target=\"_blank\">NUCLEAR RESEARCH AND CONSULTANCY GROUP<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">The Netherlands<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"http:\/\/www.ugent.be\/en\" target=\"_blank\">Universiteit Gent<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Belgium<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"http:\/\/www.unipi.it\" target=\"_blank\">Universit\u00e0 degli Studi di Pisa<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Italy<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"https:\/\/www.vki.ac.be\/\" target=\"_blank\">The von karman Institute for Fluid Dynamics<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Belgium<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"http:\/\/ec.europa.eu\/dgs\/jrc\/index.cfm\" target=\"_blank\">European Commission Joint Research Centre<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Belgium<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"http:\/\/www.psi.ch\" target=\"_blank\">Paul Scherrer Institut<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Switzerland<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n\n  <tr>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\"><a href=\"http:\/\/www.chalmers.se\/en\/Pages\/default.aspx\" target=\"_blank\">Chalmers University Of Technology<\/a><\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Sweden<\/td>\n    <td style=\"border: 1px solid #ddd; padding: 8px;\">Contractor<\/td>\n  <\/tr>\n<\/table>","team_members":[],"proj_website":"http:\/\/search.sckcen.be\/en","project_status":"Completed","project_coordinator":[{"ID":10304,"post_author":"4","post_date":"2025-06-30 17:24:42","post_date_gmt":"2025-06-30 15:24:42","post_content":"Publications: https:\/\/publications.crs4.it\/pubdocs\/index.php?idAuthor=665      Vincent Moreau, senior researcher at CRS4, takes his degree in Numerical Analysis at Paris-XI University in 1990, makes his one year Scientific Service at ONERA on atmospheric lightning numerical modeling and undergoes a Ph.D. thesis at Paris-XI, presented in 1994, on \"Functional Analysis applied to pseudo-Newtonian flows\".  In 1995, he works at ENEL-CRT of Pisa on two-phase flow simulation and modeling.  He arrives at CRS4 in 1996 where he works on fluid-structure interaction. Since 1997, he works in the ADS field, making CFD simulations and analysis, participating to the FP5 PDS-XADS, FP6 EUROTRANS, FP7 THINS, CDT, SEARCH and MAXSIMA, and H2020 PASCAL and PATRICIA European projects. Between 2002 and 2014, he also works occasionally on turbulent combustion simulation. From 2015 to 2019 still by means of CFD analysis, he contributes in the H2020 framework to the MYRTE project on high level waste transmutation and to the SESAME project on the criticalities of the liquid metal fluid-dynamics for applications to the clean nuclear power of the future. Currently, still in the same field of activity, he contributes to the European Projects LESTO, TRANSPARANT and ANSELMUS as well as FALCON consortium.","post_title":"Vincent Moreau","post_excerpt":"","post_status":"publish","comment_status":"closed","ping_status":"closed","post_password":"","post_name":"vincent-moreau","to_ping":"","pinged":"","post_modified":"2026-04-06 19:12:37","post_modified_gmt":"2026-04-06 17:12:37","post_content_filtered":"","post_parent":0,"guid":"https:\/\/www.crs4.it\/people\/vincent-moreau\/","menu_order":0,"post_type":"people","post_mime_type":"","comment_count":"0","filter":"raw"}]},"yoast_head":"<!-- This site is optimized with the Yoast SEO plugin v25.9 - https:\/\/yoast.com\/wordpress\/plugins\/seo\/ -->\n<title>SEARCH - CRS4<\/title>\n<meta name=\"robots\" content=\"index, follow, max-snippet:-1, max-image-preview:large, max-video-preview:-1\" \/>\n<link rel=\"canonical\" href=\"https:\/\/www.crs4.it\/en\/projects\/search\/\" \/>\n<meta property=\"og:locale\" content=\"en_US\" \/>\n<meta property=\"og:type\" content=\"article\" \/>\n<meta property=\"og:title\" content=\"SEARCH - CRS4\" \/>\n<meta property=\"og:description\" content=\"The goal of the SEARCH proposal is to group critical safety related research focussed on the coolability of the fuel with and without forced convection, the chemical behaviour of the heavy liquid metal reactor coolant and impurities, the interaction of fuel with the coolant and the behaviour of (volatile) radioisotopes in the coolant. 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