NURESAFE EUROPEAN PROJECT Second General Seminar



Similar documents
Qualification of Thermal hydraulic codes within NURESIM D. Bestion (CEA, France)

CFD Topics at the US Nuclear Regulatory Commission. Christopher Boyd, Ghani Zigh Office of Nuclear Regulatory Research June 2008

Preliminary validation of the APROS 3-D core model of the new Loviisa NPP training simulator

Dynamic Behavior of BWR

7.1 General Events resulting in pressure increase 5

BEST-ESTIMATE TRANSIENT ANALYSIS WITH SKETCH-INS/TRAC-BF1, ASSESSMENT AGAINST OECD/NEA BWR TURBINE TRIP BENCHMARK ABSTRACT

CASL: Consortium for the Advanced Simulation of Light Water Reactors: Program Update

CFD Code Validation Against Stratified Air-Water Flow Experimental Data

SCDAP/RELAP5-3D : A State-of-the-Art Tool for Severe Accident Analyses

Loviisa 3 unique possibility for large scale CHP generation and CO 2 reductions. Nici Bergroth, Fortum Oyj FORS-seminar

Introductions: Dr. Stephen P. Schultz

Boiling Water Reactor Systems

Research Article Validation of NEPTUNE-CFD Two-Phase Flow Models Using Experimental Data

Operational Reactor Safety /22.903

Adaptation and validation of OpenFOAM CFD-solvers for nuclear safety related flow simulations

Numerical Simulation of Thermal Stratification in Cold Legs by Using OpenFOAM

May 23, 2011 Tokyo Electric Power Company

Curriculum Vitae Dr.-Ing. Víctor Hugo Sánchez Espinoza

WORLD ASSOCIATION OF NUCLEAR OPERATORS. Performance Indicators

Nuclear Design Practices and the Case of Loviisa 3

SALOME-CFD: EDF S REFERENCE PLATFORM FOR CFD STUDIES

Nuclear Energy: Nuclear Energy

CFD simulation of fibre material transport in a PWR core under loss of coolant conditions

BWR Description Jacopo Buongiorno Associate Professor of Nuclear Science and Engineering

Boiling Water Reactor Simulator with Active Safety Systems

NEW NUCLEAR POWER PLANT UNIT IN FINLAND ACCEPTED BY THE FINNISH PARLIAMENT

Introduction to Nuclear Fuel Cycle and Advanced Nuclear Fuels

Swiss media visit to Olkiluoto August 15, 2014

HEALTH & SAFETY EXECUTIVE NUCLEAR DIRECTORATE ASSESSMENT REPORT. New Reactor Build. EDF/AREVA EPR Step 2 PSA Assessment

L.S. de Carvalho, J. M de Oliveira Neto 1. INTRODUCTION IAEA-CN-164-5P01

FIRE RISK ASSESSMENT IN GERMANY - PROCEDURE, DATA, RESULTS -

NUCLEAR SCIENCE AND ENGINEERING

Achim Beisiegel Fouad El-Rharbaoui Michael Wich. AREVA GmbH, Technical Center, Karlstein, Seligenstädter Strasse 100, Germany

SOLVING REACTOR WATER CLEAN-UP SYSTEM ANOMALIES USING RELAP5 MOD3.3

The Safety of Borssele Nuclear Power Station

Development Study of Nuclear Power Plants for the 21st Century

Numerical Investigation of Natural Circulation During a Small Break LOCA Scenarios in a PWR-System Using the TRACE v5.0 Code

DEVELOPMENT OF A DYNAMIC SIMULATION MODE IN SERPENT 2 MONTE CARLO CODE

C. starting positive displacement pumps with the discharge valve closed.

Operating Performance: Accident Management: Severe Accident Management Programs for Nuclear Reactors REGDOC-2.3.2

Generation IV Fast Reactors. Dr Richard Stainsby AMEC

AoDI. December 9, 2015 NOC-AE CFR U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC

Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]

21. TESTING AND COMPUTER CODE EVALUATION

EMERGENCY PREPAREDNESS FREQUENTLY ASKED QUESTION (EPFAQ) NEI REVISIONS 4 THROUGH 6; NUMARC/NESP 007

DIPE: DETERMINATION OF INPUT PARAMETERS UNCERTAINTIES METHODOLOGY APPLIED TO CATHARE V2.5_1 THERMAL-HYDRAULICS CODE

June 27, Scott C. Flanders, Director Division of Site Safety and Environmental Analysis Office of New Reactors

CFD Simulation of Subcooled Flow Boiling using OpenFOAM

SAMPLE CHAPTERS UNESCO EOLSS

. Space-time Analysis code for AHWR

Results and Insights of Internal Fire and Internal Flood Analyses of the Surry Unit 1 Nuclear Power Plant during Mid-Loop Operations*

VALIDATION OF THE CFD CODE NEPTUNE FOR A FULL SCALE SIMULATOR FOR DECAY HEAT REMOVAL SYSTEMS WITH IN-POOL HEAT EXCHANGERS

Accidents of loss of flow for the ETTR-2 reactor: deterministic analysis

Study Plan. MASTER IN (Energy Management) (Thesis Track)

Nuclear Education & Training in France. Support to Newcomer and Expanding Countries

EMERGENCY RESPONSE FOR THE AREA SURROUNDING THE CATTENOM NUCLEAR POWER PLANT

ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT NUCLEAR ENERGY AGENCY

INTRODUCTION. The ANSWERS Software Service WIMS AEA Technology plc

Analysis of In-Vessel Retention and Ex-Vessel Fuel Coolant Interaction for AP1000

V K Raina. Reactor Group, BARC

Nuclear power plant systems, structures and components and their safety classification. 1 General 3. 2 Safety classes 3. 3 Classification criteria 3

Conventional Energy Sources

ESPOO 2006 VTT RESEARCH NOTES 2363 SAFIR. The Finnish Research Programme on Nuclear Power Plant Safety Final Report SAFIR

Computational Fluid Dynamics Research Projects at Cenaero (2011)

Benchmarking COMSOL Multiphysics 3.5a CFD problems

Master of Engineering in Sustainable Energy Engineering

International Master of Science Degree Program

Public SUMMARY OF EU STRESS TEST FOR LOVIISA NUCLEAR POWER PLANT

RESULTS OF R&D ON FUTURE FUEL CYCLE AND ASSOCIATED HL WASTE DISPOSAL: THE FRENCH CASE

Fukushima Fukushima Daiichi accident. Nuclear fission. Distribution of energy. Fission product distribution. Nuclear fuel

Process data validation in CCGT and nuclear power plants

10 Novembre 2011 ENEA - Via Giulio Romano 41, Roma

SAFETY STANDARDS. of the. Nuclear Safety Standards Commission (KTA) KTA Residual Heat Removal Systems of Light Water Reactors.

Natural circulation in water cooled nuclear power plants

Status on Spanish Regulations and Industry. actions related to Filtered Containment. Venting Systems (FCVS)

THREE MILE ISLAND ACCIDENT

Sensitivity Studies of Modular High-Temperature Gas-Cooled Reactor (MHTGR) Postulated Accidents

A PROCESS-INHERENT, ULTIMATE-SAFETY (PIUS), BOILING-WATER REACTOR

Application of ATHENA/RELAP to Fusion Loss-of-cooling Accidents

Giorgio Bornia. Research statement. Primary interests

CFD Analysis Of Multi-Phase Flow And Its Measurements

New legislation in the nuclear field in Sweden

Accident Tolerant LWR Fuels - Update and Status. David Henderson, Acting Director, Fuel Cycle R&D Office of Nuclear Energy.

Investigations of a Long-Distance 1000 MW Heat Transport System with APROS Simulation Software

List of Papers. This thesis is based on the following papers, which are referred to in the text by their Roman numerals.

Belgian Stress tests specifications Applicable to power reactors 17 May 2011

Source Term Determination Methods of the Slovenian Nuclear Safety Administration Emergency Response Team

Transcription:

NURESAFE EUROPEAN PROJECT Second General Seminar Brussels, Belgium November 4-5, 2015 Announcement and Proposed Program

Background and Purpose of the Meeting The NURESAFE European project aims at delivering a reliable up to date software capacity usable for safety analysis needs and to further improve the safety culture by developing a high level of expertise in the proper use of the most recent and most advanced simulation tools. This software capacity will be based on the NURESIM European simulation platform (figure 1). The NURESAFE project is conducted by 23 European partners from 2013. Figure 1- The NURESIM platform The Second NURESAFE Seminar will be the opportunity to present the new methods, models and functionalities achieved during the project by the 23 NURESAFE partners and to discuss them with the community involved in Numerical Simulation of reactors: developers, stakeholders, end-users... A registration webpage is made available for the participants to the Seminar: https://docs.google.com/forms/d/1ogylvy5yv2xesv-ihdz6dn3gv552lmvnhxal61qp4- o/viewform The NURESAFE project addresses safety of light water reactors (LWR). In order to enhance the computational capacities to predict safety-relevant parameters with more accuracy and more reliability, individual models, solvers, codes and coupled applications, are run and validated through modeling situation targets corresponding to nuclear reactor situations and including

reference calculations, experiments, and plant data. As safety analysis is the main issue within the project, all these situation targets consist in some accidental scenarios. The challenging selected situation targets have been selected with respect to their potential for two-way coupling. These situation targets cover five areas: PWR and VVER main steam line break (MSLB), BWR anticipated transient without scram (ATWS), Loss of coolant accident (LOCA) in PWR, Pressurized thermal shock in PWR, BWR thermal-hydraulics issues. Scope and technical content of the seminar Features of the NURESIM software platform PWR and VVER Main Steam Line Break - Advanced dynamic nodal Neutronics-Thermalhydraulics coupling - Neutronics-thermalhydraulics coupling at the pin-cell level - Dynamic system-cfd thermalhydraulics coupling - Thermomechanics-thermalhydraulics-neutronics coupling at the pin cell level. BWR Anticipated Transient Without Scram - Peach Bottom benchmark: Advanced Turbine trip simulation and uncertainty quantification

Advanced 2-phase CFD modeling for LWR core thermal-hydraulics - ITM coupling with phase-average models - Wall heat transfer modeling of pool and convective boiling flows - DNS/LES of bubbly flows - Validation of new models implemented in the CFD platform codes Loss of coolant accident (LOCA) in PWR - Use of CFD as support to system codes for LOCA modeling in a multi-scale approach - Revisiting critical flow, CCFL, reflooding - Advanced fuel modeling - Sensitivity and uncertainty analysis applied to system codes Pressurized Thermal Shock in PWR (PTS) - 2-phase CFD modeling for PTS analysis, - Sensitivity and uncertainty methods applied to CFD codes BWR thermal-hydraulics issues - BWR core thermal-hydraulics modeling at the CFD scale - CFD modeling of direct contact condensation in the pressure suppression pool Organization of the meeting The seminar is organized around: - Scientific presentations by the NURESAFE partners - Discussions : all participants will be invited to present their experience in multi-physics and thermal-hydraulics development, validation and use, and to give their views on the NURESAFE developments Participation to the meeting The participation in the meeting is free and open to all people having an interest in Nuclear Safety or Reactor Simulation.

Preliminary agenda of the meeting Day 1 November 4 th, 2015 (all day) - Multi-physics: PWR MSLB, BWR turbine trip - Presentation of the NURESAFE Software platform - LOCA multi-scale modeling - BWR thermal-hydraulics issues - Pressurized thermal Shock modeling Day 2 November 5 th, 2015 (only morning) - Advanced two-phases CFD LWR core modeling Venue BRUSSELS 44 CENTER (www.b44c.com/) Boulevard du Jardin Botanique 44, 1000 Bruxelles, Belgium, metro BOTANIQUE Contact and registrations A registration webpage is made available for the participants to the Seminar: https://docs.google.com/forms/d/1ogylvy5yv2xesv-ihdz6dn3gv552lmvnhxal61qp4-o/viewform Inquiries about registrations can be made to: Patricia HO HUNE LGI Consulting PARIS e-mail: patricia.hohune@lgi-consulting.com OR Bruno CHANARON CEA SACLAY (France) e-mail: Bruno.chanaron@cea.fr