1. Work Package 2 Giacomo Grasso ENEA UTFISSM-PRONOC LEADER Work Package 2 meeting Madrid, May 8, 2012 Current status and organization of the work

2. Outline Status of the activities ELFR domain ALFRED domain Planning (and timing) of future work

3. The objectives of WP2 have been declared in the “LEADER Work Package 2 Work Program” The same document also lists the activities required to reach these objectives, and the timing originally foreseen for the project. Parallel activities are needed for the core design of the ELFR and ALFRED. Significant delay has been accumulated so far in both domains. Status of the activities

4. ELFR domain Core design performed Complete core characterization completed Core data provided to WP5 (“LFR database for safety analyses”)  Complete Thermal/Hydraulic analysis not yet finished Mechanical design performed  Radiation damage analysis not yet performed  Transition from start-up to equilibrium core underway Task 2.1 Task 2.3 Task 2.4 Task 2.5 Task 2.1

5. ALFRED domain Core design performed Complete core characterization completed Core data provided to WP5 (“ALFRED database for safety analyses”)  Complete Thermal/Hydraulic analysis almost done, report in progress Mechanical design performed  Radiation damage analysis performed, finalizing the report Task 2.2 Task 2.3 Task 2.4 Task 2.5

6. DocumentResponsibleEMMDueOther participants Del 05Task 2.1 (JRC-IE)15March 31 st, 2011ANN, AGH, ENEA, KIT-G, INR Del 07Task 2.2 (ENEA)26September 30 th, 2011ANN, CEA, CIRTEN, KIT-G, INR, SCKCEN Del 27Task 2.2 (ENEA)1March 31 st, 2013- Del 28Task 2.1 (JRC-IE)3March 31 st, 2013ENEA Doc 54Task 2.4 (SRS)5.5December 31 st, 2011- Doc 55Task 2.1 (JRC-IE)13March 31 st, 2012ENEA, KIT-G, INR Doc 56Task 2.3 (PSI)13March 31 st, 2012CIRTEN, ENEA, NRG, SRS, UJV Doc 60Task 2.4 (SRS)5.5June 30 th, 2012- Doc 61Task 2.5 (INR)11June 30 th, 2012ENEA Doc 62Task 2.3 (PSI)13September 30 th, 2012CIRTEN, ENEA, NRG, SRS, UJV Doc 65Task 2.5 (INR)11December 31 st, 2012SCKCEN Docs organization

7. WP2 timing Mil 02 Mil 03Mil 09

8. Coming up to an end…

9. Annex I Task 2.1 ELSY review and conceptual ELFR industrial plant neutronic characterization The activities of Task 2.1 will take the move from a critical review of the final FP6 ELSY core configuration, in conjunction with WP1, so as to point out the open issues and possible solutions/strategies to overcome these. A new reference configuration – at conceptual level – of the LFR industrial plant will be then proposed, taking also into account the aim at operating such system as an adiabatic reactor. Two alternative configurations will be also conceived about the reference core (fuelled by reference MOX), at first supposing the fuel is added by an equilibrium content of MA (expected 1.1% on HM), and then assuming all the transuranic elements (TRU) have come to complete equilibrium, as stated by the adiabaticity criterion (expected 1.3% MA on HM). These alternative configurations will be analysed focusing on the outlining of possible cycle strategies (in conjunction with WP1), evaluating the corresponding flow of wastes and related radiological and thermal loads; and on the estimation of the impact of the inclusion of MA on the core kinetics, by determining the dependence of the main reactivity coefficients (such as the void effect, the coolant temperature coefficient, the Doppler coefficient and core expansion coefficients) on the abundance of MA in the fuel.

10. Annex I Task 2.2 Criteria for scaling down to the ETDR and its neutronic characterization The preliminary activities of Task 2.2 (in conjunction with WP1) will be focused on the definition of the criteria for the consistency between ALFRED and LFR core parameters, according to the demonstration aims and main goals of the ETDR. The ALFRED core will be characterized neutronically at Beginning of Life (BoL), Beginning of Cycle (BoC) and End of Cycle (EoC), assessing the power distribution, control rods positioning (and strategy), burn up reactivity swing and cycle strategy for the system. Finally, the main reactivity coefficients (such as void coefficient, coolant temperature coefficient, Doppler coefficient and core expansion coefficients) will be evaluated at BoC and EoC, and simplified point kinetic analyses will be performed to investigate the dynamic behaviour of the system to what concerns its stability. Sensitivity analyses of the main core parameters vs nuclear data will be made in order to estimate their contributions to the uncertainties affecting the safety-related and performance coefficients.

11. Annex I Task 2.3 Thermal-hydraulics analysis of the LFR and ETDR The activity of Task 2.3 is the thermal-hydraulic assessment of the cores of both the LFR industrial plant and ALFRED, so as to provide an updated feedback to the fuel pin and fuel assembly design of such systems. In particular, static and transient analyses of the cores will be performed, focused on the identification of possible hot spots – both on the cladding and the fuel – and on the evaluation of natural circulation regimes in case of loss of flow. Task 2.4 Mechanical design and drawings of LFR and ETDR The main activity of Task 2.4 is the mechanical design – up to the production of detailed mechanical drawings – of the fuel pin, fuel assembly and whole core of both the LFR industrial plant and ALFRED, complying with the physical and technological requirements issued by all the Tasks of this Work Package (and WP3).

12. Annex I Task 2.5 DPA and radiological protection for LFR and ETDR Task 2.5 activities are related to the evaluation of the standard damage parameter for nuclear materials, the DPA (displacements/atom), and radiological loads for both the LFR industrial plant and the ETDR. In particular, for the LFR industrial plant the DPA rates will be evaluated in a few of the most critical regions of the main system structures, replaceable or not. For ALFRED, the evaluation of the DPA rates will be performed on the main components of the system, as well as the radiological doses will be evaluated in key positions of the system for personnel radioprotection. The activation estimation will allow also the characterization and the classification of the different components for waste management point of view. The results obtained by this analysis will be used for assessing the design of the shielding structures.

13. Annex II D05 - Reference MOX without MA: definition of the LFR core and neutronic characterization (M 12) This Deliverable reports the reference core configuration for the LFR industrial plant together with its preliminary neutronic characterization, obtained as a result of the critical review of the FP6 ELSY system. This configuration refers to a reactor operating with reference fuel (standard MOX) without MA. D07 - Definition of the ETDR core and neutronic characterization (M 18) This Deliverable reports the ALFRED core configuration, with a complete neutronic characterization to what concerns criticality and power distribution assessment, cycle strategy and related criticality swing, and control rod positioning and operation strategy. D27 - ETDR core. Summary, synoptic tables, conclusions and recommendations (M 36) This Deliverable, intended for public dissemination of the work, collects the main characteristics, features and issues of the final ALFRED core, providing conclusive remarks of the whole activity and recommendations for a further development of the study.

14. Annex II D28 - LFR cores. Summary, synoptic tables, conclusions and recommendations (M 36) This Deliverable, intended for public dissemination of the work, collects the main characteristics, features and issues of the proposed core configurations of the LFR industrial plant, providing conclusive remarks of the whole activity and recommendations for a further development of the study. T54 - Mechanical design and drawings of ETDR pin/assembly/core (M 21) This Technical Document represents the official reference for the ALFRED reactor design, providing to every Task the detailed mechanical drawings of the fuel pin, fuel assembly and whole core. T55 - Adiabatic-LFR (equilibrium MOX with equilibrium MA): preliminary definition of the core and neutronic characterization (M 24) This Technical Document provides the neutronic characterization of the core for the LFR configuration to be operated as an adiabatic reactor. It also reports the impact of the inclusion of MA in the fuel on the main kinetic parameters by means of preliminary dynamic analyses, as well as a preliminary evaluation of the flow of both feed and waste materials in the related closed fuel cycle, together with the results of their radiological and thermal load evaluations.

15. Annex II T56 - Thermal-hydraulics assessment of the ETDR core (M 24) This Technical Document provides the results of the detailed static and transient thermal- hydraulic analyses of the ALFRED core to be used for assessing the final configuration of the system. T60 - Mechanical design and drawings of LFR pin/assemblies/cores (M 27) This Technical Document represents the official reference for the different LFR industrial plant designs, providing to every Task the detailed mechanical drawings of the fuel pin, fuel assembly and whole core layout of the LFR configurations. T61 - ETDR core: DPA rates in the main components, activation, doses (M 27) This Technical Document reports the results of the DPA and radiologic analyses on the main components of the ALFRED system, to be used for assessing the design of the shielding structures.

16. Annex II T62 - Thermal-hydraulics assessment of the LFR cores (M 30) This Technical Document provides the results of the detailed static and transient thermal- hydraulic analyses of the industrial LFR cores to be used for assessing the final configurations of the system. T65 - LFR cores: DPA rates in the main components, activation, doses (M 33) This Technical Document reports the results of the DPA analysis on the main components of the industrial LFR system.

17. Annex III DocumentResponsible EMM Budget Participant Man Months ANNANN AGHAGH CEACEA CIRTCIRT ENEAENEA KITKIT INRINR JRCJRC NRGNRG PSIPSI SCKSCK SRSSRS UJVUJV Del 05Task 2.1 (JRC-IE)1516--3212----- Del 07Task 2.2 (ENEA)261-52715---5-- Del 27Task 2.2 (ENEA)1----1-------- Del 28Task 2.1 (JRC-IE)3----1--2----- Doc 54Task 2.4 (SRS)5.5-----------5½- Doc 55Task 2.1 (JRC-IE)13----4441----- Doc 56Task 2.3 (PSI)13---11---33-32 Doc 60Task 2.4 (SRS)5.5-----------5½- Doc 61Task 2.5 (INR)11----1-10------ Doc 62Task 2.3 (PSI)13---21---23-32 Doc 65Task 2.5 (INR)11------10---1-- TOTAL2655197305566174