10 Novembre 2011 ENEA - Via Giulio Romano 41, Roma

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1 UNIVERSITÀ DI PISA GRUPPO DI RICERCA NUCLEARE SAN PIERO A GRADO (GRNSPG) Il reattore sperimentale per applicazioni scientifiche e industriali Novembre 2 ENEA - Via Giulio Romano 4, Roma Competenze ItalianeUtili per il Progetto JHR e Opportunità di Ricerca per il Mondo Accademico Martina Adorni, Dino Araneo, Nikolaus Muellner, Francesco D Auria Any reproduction, alteration, transmission to any third party or publication in whole or in part of this document and/or its content is prohibited unless the University of Pisa ro a Grado Nuclear Research Group has provided its prior and written consent. This document and any information it contains shall not be used for any other purpose than the one for which they were provided. Legal action may be taken against any infringer and/or any person breaching the aforementioned obligations.

2 rado The GRNSPG The ro a Grado Nuclear Research Group Born in December 2, aims at maintaining and improving the Italian competences in the field of the nuclear technology with particular reference to Nuclear Power Plants. Performs R&D, engineering services, education and training activities, according to the tradition of the Department of Mechanics, Nuclear and Production Engineering (DIMNP) and of the University of Pisa (UNIPI). Led by Prof. Francesco D Auria, DAuria, involves more than people (mostly PhD level) among full and part time staff and International Experts. Located in a high tech, comfortable and well connected site, shared with other research labs (e.g. BIOLAB, INFN)., Novembre 2, ENEA Via Giulio Romano 4, Roma 2/

3 JULES HOROWITZ REACTOR FONESYS Q Quality y Assurance Education dt i i and Training Networks of E ll Excellence GRNSPG Editorial ti iti activities Nuclear Reactor Technology: Safety &D i & Design Innovation AVAILABLE CODES Relap5/D ANSYS-CFX-. D NK - Nestle XSEC derivation Rel evant ph ph. Criteria & Acceptabili ty Thres holds TransUranus Phenomena consideration Most suited (BE) code Consideration of qualification: Nodalization development - Code - Nodalization - User 4 5 Select Accept. Criteria 2 Assumptions on BIC Criter ia Criteria 7 SA Computational Platform Analysis CA Coupling with the SYS TH code RA Purposes 8 Scenario selection Atucha II Safety Margins Performing the analysis U Quantification? Uncertainty and sensitivity studies Acceptability criteria CA RA FSAR CIAU & BF method EM/Component Stress An. Results Diagram 5.-: International Organizations Transient core power distribution EM/Radiological Consequences CFD CFX Boron distribution in moderator tank Linear Heat Rate (kw/m) LA LD LG AL 2 5 AC Y AF 5 AK BE X 27 BB 2 42 TH RELAP5-D Linear heat rate Fast neutron flux Analysis of AOO/DBA/SBDBA Cladding temperature Coolant pressure BB 7 58 BA 8 52 BL 52 AK AG AC 488 AB AA L D L C BB 25 8 BA 25 2 AK AH BL AG AD 5 5 Fuel Performance/Behavior 7 AB 8 AA AL 2 LK AC AF 4 AE BD BC BE BF L A L B BG L E AL L K 2 L H 2 L G 22 L F AF 4 5 AE 4 AD AH LH LD 7 2 LC LA Depletion PUMA Burn up 8 Oxidation at high temperature 7 ~ C C B ittl Failure Brittle F il TRANSURANUS 2 7 LB LF 2 4 LE LG 7 8 ~ 5 kw/m Embrittlement of Cladding NUMBER OF FAILED RODS 4 2 Burnup distribution Linear Heat Rate BG 2 BF BE 4 BD 5 BC Temperaturee Experimental Activities Simplified flowchart for the proposed BEPU approach for Atucha II accident analysis D-NK NESTLE 45 ppo Riceerca Nu San Pieero a Grrado The GRNSPG world of competence - FUEL SAFETY CRITERIA Time [s] # and id of failed rods JULES HOROWITZ REACTOR, Novembre 2, ENEA Via Giulio Romano 4, Roma 2 Possible fracture during quenching Ballooning / Rupture Fission Release and Transport Dose calculations MELCOR MAACS /

4 rado Specific Competences Related to RRs International Projects: IAEA expert missions Participation i to Coordinated dresearch hprojects Participation to Benchmarks Preparation of Technical Documents OECD Activities: Working Group on Fuel Safety Participation to Benchmarks Pubblications: More than 5 in International Journals More than Conference Proceedings More than 2 Technical Reports, Novembre 2, ENEA Via Giulio Romano 4, Roma 4/

5 NUTEMA rado Nuclear Power Plant Technology Knowledge Management System or Nuclear Technology Master Goal INTEGRATED SYSTEM CAPABLE OF MANAGING THE OVERALL NPP/RR KNOWLEDGE AND EXPERTISE NEEDED FOR A SAFETY USE OF NUCLEAR TECHNOLOGY THROUGH THE FULL LIFE OF AN NPP/RR Main target Utilities: NPP KNOWLEDGE CONSTRUCTION MANAGEMENT MODIFICATION MANAGEMENT OPERATION & MAINTENACE MANAGEMENT LICENSING PERSONNEL LEARNING DESIGN AUTHORITY ROLE Principle Defense-In-Depth Depth, Novembre 2, ENEA Via Giulio Romano 4, Roma 5/

6 rado WORKING MODES NUTEMA NUTEMA NUTEMA DISCIPLINES Nuclear Power Plant Technology Knowledge Management System Or NPP LIFETIME DATABASE & COMPUTATIONAL TOOLS Nuclear Technology Master Nuclear Power Plant Technology Knowledge Management System OBJECTIVE /TARGETS SCOPE /INSPIRATION Or L Financing OBJECTIVE SStructural Mechanics BComponents, Materials TO MANAGE AND TO PRESERVE THE KNOWLEDGE /TARGETS ASSOCIATED WITH DESIGN, CONSTRUCTION AND OPERATION OF NPP COMPLEX SYSTEMS &St Structures t - DMS MDesign T Neutron Physics N Construction Nuclear Technology SCOPE DESIGN AUTHORITY U IRIDM Thermalhydraulics Master INTEGRATED RISK CRISIS CENTER CENDF /INSPIRATION (IAEA INSAG ) INFORMED DECISION MAKING or O Commissioning BASES support (IAEA INSAG 25) support EMERGENCY PREPARADNESSS DNJOY V Radioprotection P Operation EMCNP NUCLEAR INDUSTRY ACTORS END USERS W Civil NAMELY Engineering UTILITIES F TRANSURANUS Q Safety & TO MANAGE AND TO PRESERVE THE KNOWLEDGE Licensing X Electronics GANSYS ASSOCIATED WORKING WITH DESIGN, CONSTRUCTION AND OPERATION DATABASE OF HRELAP NPP COMPLEX SYSTEMS MODES NPP LIFETIME DISCIPLINES & R Decommissionin o Y Informatics COMPUTATIONAL TOOLS I NESTLE g Z Chemistry J MACCS RODOS L Financing AA SStructural. Mechanics BComponents, Materials DESIGN AUTHORITY IRIDM INTEGRATED RISK K & Structures - DMS CRISIS CENTER (IAEA INSAG ) INFORMED DECISION MAKING or BASES support (IAEA INSAG 25) support INTERACTIVE TRAINING EMERGENCY PREPARADNESSS END USERS MDesign NConstruction OCommissioning P Operation Q Safety & Licensing R Decommissionin g T Neutron Physics U Thermalhydraulics V Radioprotection W Civil Engineering X Electronics Y Informatics Z Chemistry AA. CENDF DNJOY EMCNP F TRANSURANUS GANSYS HRELAP I NESTLE J MACCS RODOS K TRAINEE NUCLEAR SUPERVISOR INDUSTRY ACTORS INSTRUCTOR NAMELY UTILITIES INTERACTIVE TRAINING TRAINEE SUPERVISOR INSTRUCTOR, Novembre 2, ENEA Via Giulio Romano 4, Roma /

7 BG BG BF BF BE BE BD BD BC BC BB BB BA BA BL BL AK AK AH AH AG AG AF AF AE AE AD AD AC AC AB AB AA AA AL AL LK LK LH LH LG LG LF LF LE LE LD LD LC LC LB LB LA LA Linear Heat Rate (kw/m) X LA LD LG AL AC Y AF AK BB BE rado Features of the System Identification of Interfaces between Computational Tools Chain of Codes as used in CNA-2 FSAR Chapter 5 «Accident Analysis» D-NK NESTLE Transient core power distribution Linear heat rate Fast neutron flux TH RELAP5-D Analysis of AOO/DBA/SBDBA Cladding temperature Coolant pressure Fuel Performance/Behavior AB AB 4 Depletion PUMA Burnup distribution Burnup Fission Release and Transport MELCOR TRANSURANUS - NUMBER OF FAILED RODS - FUEL SAFETY CRITERIA # and id of failed rods Brittle Failure ~ 5 kw/m Dose calculations Temperature MAACS, Novembre 2, ENEA Via Giulio Romano 4, Roma CFD CFX Boron distribution in moderator tank Oxidation at high temperature ~ C Ballooning / Rupture Embrittlement of Cladding Possible fracture during quenching Time [s] 8 7 Linear Heat Rate /

8 The System, Novembre 2, ENEA Via Giulio Romano 4, Roma 8/ rado

9 JULES HOROWITZ REACTOR ppo Riceerca Nu San Pieero a Grrado The System STATUS: The working modality as the database and/or management of computational tools have been proved at the present time, including a few thousands files (data base), a couple of dozen system codes and a few tens of input decks installed. The mode of p y p operation Safety is possible. JULES HOROWITZ REACTOR, Novembre 2, ENEA Via Giulio Romano 4, Roma /

10 Conclusions rado NUTEMA constitutes an integrated system capable of managing gthe overall NPP/RR knowledge and expertise needed for a safety use of nuclear technology. The exploitation of the planned capabilities of NUTEMA will require an additional effort. However in the existing configuration the system may already be used to support the Jules Horowitz Reactor analysis, including training and qualification for any level staff. UNIPI GRNSPG is interested in material testing, and can contribute with the design and analysis of results due to the importance for the development and the qualification of materials and nuclear fuel used in the nuclear industry. UNIPI GRNSPG will contribute providing man power., Novembre 2, ENEA Via Giulio Romano 4, Roma /

11 rado radothanks FOR YOUR ATTENTION! i i it, Novembre 2, ENEA Via Giulio Romano 4, Roma /

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