Multi-Physics Multi-Scale LWR Simulations

Transcription

1 STARS Overview Multi-Physics Multi-Scale LWR Simulations Conduct Research Contribute to Education Provide Scientific Support /LRS /STARS/FH41 ( 8 / 14 )

2 STARS Code System Nuclear Computation Lab Course Familiarization with usage of selected codes /LRS /STARS/FH41 ( 9 / 14 )

3 Scope and Objectives MSc Proposal 1 Fuel Assembly Thermal-Hydraulics Comparative Assessment of COBRA-TF and TRACE for CHF Analyses Evaluation of Coarse-Mesh System Code vs. Fine-Mesh Sub-Channel code predictions of Boiling Crisis Development of System Code and Sub-Channel models for representative modern PWR Fuel Assembly Designs Development of associated Application Programming Interfaces (APIs) for automated modelling and pre/pros processing Validation against Experimental PWR CHF Data (OECD/NEA PBSBT) Quantify the added-value of using Sub-Channel versus System Code for CHF Codes and Relevance TRACE (System Code) COBRA-TF (Sub-Channel Code) Thermal Limits and Transient CHF Direct Safety Relevance (Core Design and Fuel failures) Topics Multi-Phase Flow and Heat Transfer Thermal Core Design Safety of Nuclear Power Plants Project Supervisor Roman Mukin Sub-channel code COBRA-TF: Sub-channel coolant analysis, but slow running Which is better? System code TRACE: Average of all coolant in assembly, coarse models, but fast running /LRS /STARS/FH41 ( 10 / 14 )

4 Scope and Objectives Assess the impact of specific level density, strength function and optical models on capture cross sections Calculate MACS (Maxwellian averaged cross sections) Compare with Hauser Feshbach classical approach Effect of Doppler broadening MSc Proposal 2 Nuclear Reaction Modelling Impact of Nuclear Models on Capture Cross Sections from the Stability to the Neutron Drip Line Codes and Relevance TALYS (Nuclear Reaction) CALENDF (Resonance Treatment) Modelling of Reactions for Neutron-rich Isotopes Topics Nuclear Physics and Reactions Resonance Behaviour and Statistical Interpretation Astrophysics and r-process Project Supervisor Dimitri Rochman /LRS /STARS/FH41 ( 11 / 14 )

5 Scope and Objectives MSc Proposal 3 Fuel Behaviour and Thermo-Mechanics Development of Uncertainty Quantification Methodology for FALCON V1 Fuel Performance Code LRS/STARS Part of the EPRI Development Team for the re-designed new Falcon V1 FEM Fuel Performance Code Establishment and Verification of Falcon V1 Methodology for Base Irradiation of Modern LWR Fuel Rod Designs Development of Post-Processing Interface to new Falcon V1 HDF5 Output Structure Coupling to URANIE Platform for Uncertainty Quantification (UQ) and Sensitivity Analysis (SA) Codes and Relevance Falcon V1 (Fuel Thermo-Mechanics) URANIE (UQSA Platform) Fuel Integrity and Reliability Best-Estimate Safety Analysis Topics Nuclear Fuels and Materials Heat Transfer and Structural Mechanics Mathematical Statistics Project Supervisor Cedric Cozzo PSI Fuel Management System Enlarge Database Develop Falcon Models Postprocess Falcon output Uranie UQ/SA Platform Define uncertainties with probability density functions Produce Matrix of Falcon Samples Uncertainty quantification (e.g. T fuel = f(bu) /LRS /STARS/FH41 ( 12 / 14 )

6 STARS On-going and Previous MSc Projects (On-Going) J. LI Dev elopm en t a n d A ssessm en t of A dv a n ced Modelin g Ca pa bilities for Ser pen t A ssem bly Depletion Ca lcu la tion s R. Sa v elli V a lida tion of PSI Flu en ce Meth odolog y for Lon g -Ter m Ir r a dia ted Dosim eter Ca psu les G. JANIN Development of optimal micro/macroscopic cross-section model for a transport pin-by-pin solver H. YA O Th er m a l-hy dr a u lic Sim u la tion of Rig -Of-Sa fety A ssessm en t Tests in La r g e Sca le Test Fa cility u sin g Upda ted TRA CE Code D. ZHA NG Bu n dle Recon str u ction Histor y Meth od for Dir ect Wh ole Cor e Ca lcu la tion s w ith th e Code n TRA CER Z. GUO A tom istic Sim u la tion s of Ir r a dia tion Da m a g e in Ch r om iu m Doped LWR Fu el L. CHUNYA N Dev elopm en t a n d Optim iza tion of Fa st Solu tion A lg or ith m s for th e Fu el Depletion Equ a tion s H. PERRIER Dev elopm en t of Hy br id CA SMO/SERPENT Deter m in istic/stoch a stic Fu el Depletion Sch em e A. DUPRE Modellin g a n d V a lida tion En h a n cem en ts of th e PSI Fa st Neu tr on Flu en ce MCNPX ba sed Com pu ta tion a l Sch em e u sin g r ecen t KKG Ex per im en ta l Da ta L. ROSSINELLI A ssessm en t of SERPENT for BWR La ttice Modellin g a n d Dev elopm en t of Cou plin g to SIMULA TE-3 Code Q. ZHOU V a lida tion of CFD Solv er s for Bu oy a n cy Dr iv en Flow s on th e ba sis of ROCOM Tests D. Ch ion is (A ssocia ted MSc) V. By kov (A ssocia ted MSc) Pea k Cla ddin g Tem per a tu r e Pr ediction a n d A ssessm en t for th e Leibsta dt NPP Usin g SIMULA TE-3 K En h a n cem en t a n d V a lida tion of BWR MCNP A ctiv a tion Sim u la tion s for Sw iss Decom m ission in g Pla n n in g S. BOGETIC Dev elopm en t a n d V er ifica tion of TRA CE/PA RCS Meth odolog y for a n a ly ses of th e Sw iss Rea ctor s D. WICA KSONO Dev elopm en t a n d A sssem en t of A dv a n ced Tem por a l Cou plin g Sch em es for TRA CE/S3 K A n a ly ses A. DUFRESNE Dev elopm en t of MCNPX-ba sed Com pu ta tion a l Sch em e for Refer en ce Nu m er ica l Estim a tion s of Hig h -En er g y PWR Con tr ol Rod Tip Flu en ce Proc. ANS 2016 Student Conference, USA, March/April, 2016 Proc. ANS 2016 Student Conference, USA, March/April, 2016 April April Annals of Nuclear Energy 2015 April 2014 Proc. NURETH-16, Chicago, USA, 2015 April 2015 April 2015 April 2013 Proc. M&C 2013, Sun Valley, USA, May 2013 Proc. PHYSOR2012, USA, 2012 R. PITTA RELLO Mon te Ca r lo a n a ly sis of RPV dosim etr y ex per im en ts Annals of Nuclear Energy 38 (2011) /LRS /STARS/FH41 ( 13 / 14 )

7 For more on STARS, please consult More details on the STARS proposals will be found here /LRS /STARS/FH41 ( 14 / 14 )