JASMIN
Joint Advanced Severe accidents Modelling and Integration for Na-cooled fast neutron reactors
| Coordinatore | INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE
Organization address
address: Avenue de la Division Leclerc 31 contact info |
| Nazionalità Coordinatore | France [FR] |
| Totale costo | 5˙650˙533 € |
| EC contributo | 2˙991˙182 € |
| Programma | FP7-EURATOM-FISSION
EURATOM: Nuclear fission and radiation protection |
| Code Call | FP7-Fission-2011 |
| Funding Scheme | CP-FP |
| Anno di inizio | 2011 |
| Periodo (anno-mese-giorno) | 2011-12-01 - 2016-05-31 |
Partecipanti
| # | ||||
|---|---|---|---|---|
| 1 |
INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE
Organization address
address: Avenue de la Division Leclerc 31 contact info |
FR (FONTENAY AUX ROSES) | coordinator | 992˙132.00 |
| 2 |
Karlsruher Institut fuer Technologie
Organization address
address: Kaiserstrasse 12 contact info |
DE (Karlsruhe) | participant | 468˙157.00 |
| 3 |
CENTRO DE INVESTIGACIONES ENERGETICAS, MEDIOAMBIENTALES Y TECNOLOGICAS-CIEMAT
Organization address
address: Avenida Complutense 22 contact info |
ES (MADRID) | participant | 391˙290.00 |
| 4 |
UNIVERSITAET STUTTGART
Organization address
address: Keplerstrasse 7 contact info |
DE (STUTTGART) | participant | 314˙880.00 |
| 5 |
JRC -JOINT RESEARCH CENTRE- EUROPEAN COMMISSION
Organization address
address: Rue de la Loi 200 contact info |
BE (BRUSSELS) | participant | 255˙400.00 |
| 6 |
AGENZIA NAZIONALE PER LE NUOVE TECNOLOGIE,L'ENERGIA E LO SVILUPPO ECONOMICO SOSTENIBILE
Organization address
address: Lungotevere Grande Ammiraglio Thaon di Revel 76 contact info |
IT (ROMA) | participant | 226˙510.00 |
| 7 |
GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT (GRS) MBH
Organization address
address: Schwertnergasse 1 contact info |
DE (KOELN) | participant | 169˙750.00 |
| 8 |
ELECTRICITE DE FRANCE S.A.
Organization address
address: avenue de Wagram 22-30 contact info |
FR (PARIS) | participant | 128˙793.00 |
| 9 |
AREVA NP SAS
Organization address
address: 1 place de la Coupole - Tour AREVA contact info |
FR (COURBEVOIE) | participant | 44˙270.00 |
Mappa
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Obiettivo del progetto (Objective)
'This project will support the ESNII (European Sustainable Nuclear Industrial Initiative) roadmap and the Strategic Research Agenda and the Deployment Strategy of SNETP (Sustainable Nuclear Energy Technology Platform) on the enhancement of Sodium-cooled Fast neutron Reactors (SFR) safety, especially towards a higher resistance to severe accidents. In the initiation phase of SFR core disruptive accidents, it is essential to investigate the impact of new core designs that may disperse core debris and minimize risks of core compaction. The available codes today have been developed in the 80’s. The objective is to develop a new European simulation code, ASTEC-Na, with improved physical models, accounting for results of recent LWR research, with modern software architecture and high flexibility to account for innovative reactor designs. It will be based on the ASTEC European code system, developed by IRSN and GRS for severe accidents in water-cooled reactors. This will allow to capitalize the state-of-the-art knowledge on SFR severe accidents. The code will evaluate the consequences of fuel pin failure conditions on materials relocation and primary system loads, and the source term produced by the migration inside the reactor of activated fission products and aerosols that may be released to the environment. The project will gather partners with strong experience on SFR safety and/or on ASTEC code. Specific SFR physical models will be developed, on the basis of outputs of the CP-ESFR FP7 project. After the elaboration of general specifications and of a validation matrix, the models will be developed, implemented into the code, validated vs. experiments (like past CABRI ones) and benchmarked with other codes. The further extension of ASTEC-Na to cover other parts of the SFR severe accidents (transition phase, fires) and to LFR will be investigated. An Education programme will include workshops as well as the secondment of young researchers in other organizations.'
Introduzione (Teaser)
Safety is a key pillar of Generation IV (Gen-IV) nuclear reactors. For this purpose, comprehensive robust and flexible modelling tools to accurately evaluate all accident scenarios and consequences in the design phase are needed.
Descrizione progetto (Article)
Scientists with EU support of the project 'Joint advanced severe accidents modelling and integration for Na-cooled fast neutron reactors' (http://www.jasmin-fp7.eu/ (JASMIN)) are now creating the required modelling tools for one of the six Gen-IV technologies slated for intense research and development.
JASMIN is building on the European Accident Source Term Evaluation Code (ASTEC) for severe accidents involving water-cooled light water reactors. The ASTEC-Na for Gen-IV sodium-cooled fast reactors (SFRs) will assess the consequences of fuel pin failure on materials migration. Additionally, potential source term, which is the radioactive material released into the environment in an accident, will also be estimated by ASTEC-Na. Besides the primary phase of severe accidents, JASMIN is also investigating other phenomena related to containment after an accident in the context of safety. Work is progressing on the four models describing sodium thermal hydraulics, thermomechanics, the source term and neutronic effects.
Within the first project period, scientists defined the specifications of ASTEC-Na and built the first validation test matrix for investigating thermal hydraulics and fuel transients. It consists of 12 out of 66 available tests with the Cabri and Scarabee research reactors that are fully dedicated to safety experimental studies. In the meantime, the team has begun populating an experimental database on sodium thermal hydraulics and fission product transport in containment. The first version of ASTEC-Na was released in September 2012 and a preliminary validation of thermal hydraulic capabilities was conducted with some Cabri and Scarabee tests. The other three models are in various stages of development, supported by literature reviews and additional experiments.
JASMIN is capitalising on 40 years of research and model development to deliver robust and flexible simulation tools. This will support the design of Gen-IV SFRs that significantly reduce the likelihood of a severe accident. The project's contribution to the development of sustainable nuclear energy will help ensure a leading role for the EU in the global arena.