Common use of References Clause in Contracts

References. [1] ▇▇▇▇▇▇, ▇., et al., 2014. The core design of ▇▇▇▇▇▇, a demonstrator for the European lead-cooled reactors, Nucl. Eng. and Des., Vol. 278, 287-301. [2] OECD/NEA, 2014. Technology Roadmap Update for Generation IV Nuclear Energy Systems, . [3] ▇▇▇▇▇▇, ▇., et al., 2014. Ottimizzazione del progetto di nocciolo di ▇▇▇▇▇▇. Ricerca di Sistema Elettrico, Technical Report ADPFISS-LP2-050. [4] Lodi, F., et al., 2015. Characterization of the new ▇▇▇▇▇▇ core configuration. Ricerca di Sistema Elettrico, Technical Report ADPFISS-LP2-085. [5] ▇▇▇▇▇▇▇▇, ▇., et al., 2002. The ERANOS code and data system for Fast Reactor neutronic analyses, Proc. Int. Conf. on the New Frontiers of Nuclear Technology: reactor physics, safety and high- performance computing, PHYSOR 2002, Seoul, Korea, October 7-10th. [6] ▇▇▇▇▇▇▇▇, ▇.▇., et al., 1995. RELAP5/MODE3 code manual, NUREG/CR–5535, INEL–95/174, Idaho National Engineering Laboratory. [7] ▇▇▇▇, ▇., et al., 2016. ANTEO+: a sub-channel code for thermal-hydraulic analysis of liquid metal cooled systems, Nucl. Eng. and Des., Vol. 301, 128-152. [8] ▇▇▇▇▇▇, ▇., et al., 2006. The ▇▇▇▇-3.1 Nuclear Data Library, NEA Data Bank, OECD, ▇▇▇▇ Report 21, NEA N_6190. [9] ▇▇▇▇▇▇▇▇, ▇., 1997. Physics documentation of Eranos: the Ecco cell code, CEA Tech. Rep. DERSPRC-LEPh-97-001. [10] ▇▇▇▇▇▇▇, ▇.▇., et al., 1993. TGV: a coarse mesh 3 dimensional diffusion-transport module for the CCRR/ERANOS code system, Tech. Rep. CEA DRNR-SPCILEPh-93-209. [11] OECD-NEA, 2011. Technical and economical aspects of load following with nuclear power plants. [12] ▇▇▇▇▇▇▇▇▇, ▇., et al., 2014. A preliminary approach to the ▇▇▇▇▇▇ control strategy, Progress in Nuclear Energy, Vol. 73, 113-128. [13] ▇▇▇▇▇▇▇▇▇▇▇▇, ▇., et al., 2014. Studi preliminari di tecniche di monitoraggio del nocciolo di ▇▇▇▇▇▇. Ricerca di Sistema Elettrico, ENEA Technical Report ADPFISS-LP2-051.

References. [1] ▇▇▇▇▇▇, ▇., et al., 2014. The core design of ▇▇▇▇▇▇, a demonstrator for the European lead-cooled reactors, . Nucl. Eng. and Des., Vol. 278, 287-301. [2] OECD/NEA, 2014. Technology Roadmap Update for Generation IV Nuclear Energy Systems, ▇▇▇.▇▇▇-▇.▇▇▇. [3] ▇▇▇▇▇▇▇▇▇, ▇., et al., 20142013. Ottimizzazione del progetto di nocciolo di Current progress and future plans of the FREYA Project. Proc. Int. Conf. Technology and Components of Accelerator Driven Systems (TCADS-2), Nantes, France, May 21-23. [4] ▇▇▇▇://▇▇▇▇▇.▇▇/▇▇/▇▇▇▇▇▇▇▇▇▇▇▇▇▇/▇▇▇▇▇▇▇▇-▇▇▇▇▇▇▇-▇▇-▇/. [5] ▇▇▇▇▇▇▇▇▇, ▇., et al., 2016. Ricerca di Sistema ElettricoSpectrum Index and Minor Actinide fission rate measurements in several fast lead critical cores in the zero power VENUS-F reactor. Proc. Int. Conf. Unifying Theory and Experiments in the ▇▇▇▇ ▇▇▇▇▇▇▇ (▇▇▇▇▇▇ ▇▇▇▇), Technical Report ADPFISS▇▇▇ ▇▇▇▇▇▇, ▇▇▇▇▇, ▇▇▇, May 1-LP2-0505. [46] Lodi▇▇▇▇▇▇▇, F.M., et al., 2015. Characterization of the new LFR mock-up definition. Deliverable D4.1 EURATOM FP7 “FREYA” project (Technical Report FSN-SICNUC-002, ENEA). [7] ▇▇▇▇▇▇ core configuration▇▇▇▇, ▇., et al., 2015. Ricerca di Sistema ElettricoLFR mock-up characterisation, Deliverable D4.2 EURATOM FP7 “FREYA” project. [8] ▇▇▇▇▇▇▇, M., et al., 2015. LFR mock-up reactivity effects, Deliverable D4.3 EURATOM FP7 “FREYA” project (Technical Report ADPFISSFSN-LP2-085SICNUC-003, ENEA). [59] ▇▇▇▇▇▇▇▇, ▇., et al., 2002. The ERANOS code and data system for Fast Reactor neutronic analyses, . Proc. Int. Conf. on the New Frontiers of Nuclear Technology: reactor physics, safety and high- high-performance computing, computing (PHYSOR 2002), Seoul, Korea, October 7-10th10. [6] ▇▇▇▇▇▇▇▇, ▇.▇., et al., 1995. RELAP5/MODE3 code manual, NUREG/CR–5535, INEL–95/174, Idaho National Engineering Laboratory. [7] ▇▇▇▇, ▇., et al., 2016. ANTEO+: a sub-channel code for thermal-hydraulic analysis of liquid metal cooled systems, Nucl. Eng. and Des., Vol. 301, 128-152. [8] ▇▇▇▇▇▇, ▇., et al., 2006. The ▇▇▇▇-3.1 Nuclear Data Library, NEA Data Bank, OECD, ▇▇▇▇ Report 21, NEA N_6190. [910] ▇▇▇▇▇▇▇▇, ▇., 1997. Physics documentation of Eranos: the Ecco cell code, CEA Tech. Rep. Technical Report DERSPRC-LEPh-97-001, CEA. [1011] ▇▇▇▇▇▇▇, ▇.▇., et al., 1993. TGV: a coarse mesh 3 dimensional diffusion-transport module for the CCRR/ERANOS code system, Tech. Rep. CEA DRNR-SPCILEPh-93-209. [11] OECD-NEA, 2011. Technical and economical aspects of load following with nuclear power plantsReport ▇▇▇▇-▇▇▇▇▇▇▇▇- ▇▇-▇▇▇, CEA. [12] ▇▇▇▇▇▇, ▇., et al., 2006. The ▇▇▇▇-3.1 Nuclear Data Library, NEA Data Bank. Technical Report ▇▇▇▇ Report 21, NEA N_6190, OECD. [13] ▇▇▇▇▇://▇▇▇-▇▇▇.▇▇▇▇.▇▇▇/▇▇▇▇▇/▇▇▇▇.▇▇▇ [14] ▇▇▇▇▇▇▇▇▇, ▇., et al., 20142011. A preliminary approach to Guinevere project: updated deterministic model by the ▇▇▇▇▇▇ control strategyERANOS French code. Technical Report UTFISSM-P9US-001, Progress in Nuclear Energy, Vol. 73, 113-128ENEA. [1315] ▇▇▇▇▇▇▇▇▇▇, M., et al., 2008. Uncertainty and target accuracy assessment for innovative systems using recent covariance data evaluations (International Evaluation Co-operation Volume 26), OECD/NEA WPEC-26 ISBN 978-92-64- 99053-1, Technical Rep. No. 6410, OECD. [16] ▇▇▇▇▇▇▇, ▇.▇., et al., 20142013. Studi preliminari di tecniche di monitoraggio del nocciolo di Initial MCNP6 Release Overview - MCNP6 version 1.0. Technical Report LA-UR-13-22934, Los Alamos National Laboratories. [17] ▇▇▇▇▇▇▇▇, ▇.▇., et al., 2006. Ricerca di Sistema Elettrico, ENEA ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology. Nucl. Data Sheets 107(12). Also in Technical Report ADPFISSUCRL-LP2JRNL-225066. [18] ▇▇▇▇▇▇▇, ▇., 2015. The VENUS-051F CC6 core: ERANOS neutronic analyses and comparison with experimental data. Presentation at EURATOM FP7 “FREYA WP3/4 meeting, Genova (I), November 12-13 (Technical Report FSN-SICNUC- 004, ENEA). [19] Losa E. and ▇▇▇▇▇▇ M., 2015. Design and preparation of experiment for validation of neutronic codes. Technical Report 1157, CVŘ. [20] ▇▇▇▇▇▇▇, ▇., 2006. Standard perturbation theory and applications. Presentation at ERANOS users’ workshop, Cadarache (F), May 29-June 2. Appendix A - Sensitivity and uncertainty analyses on keff value