III. Otras disposiciones. CONSEJO DE SEGURIDAD NUCLEAR. Comunidad Autónoma de Cataluña. Convenio. (BOE-A-2024-212)
Resolución de 26 de diciembre de 2023, del Consejo de Seguridad Nuclear, por la que se publica el Convenio con la Universitat Politècnica de Cataluña, para el desarrollo del proyecto de I+D+i ITHEM ("Técnicas de incertidumbre, termohidráulica avanzada y escalado en metodología de análisis de accidentes").
19 páginas totales
Página
BOLETÍN OFICIAL DEL ESTADO
Núm. 3
Miércoles 3 de enero de 2024
Sec. III. Pág. 1097
ANEXO 2
Memoria Económica
1.
Duración del proyecto.
La duración de este proyecto de I+D será de cuatro años.
cve: BOE-A-2024-212
Verificable en https://www.boe.es
[22] M. Dusic, M. Dutton, H. Glaeser, J. Herb, J. Hortal, R. Mendizábal, F. Pelayo,
«Combining insights from probabilistic and deterministic safety analyses in option 4 from
the IAEA specific safety guide SSG-2,» Nucl. Technol., vol. 188, no. 1, pp. 63–77, 2014.
[23] A. N. Society, Ed., ANSI/ANS-51.1-1983 Nuclear Safety Criteria for the Design
of Stationary Pressurized Water Reactor Plants. La Grange Park, Illinois, 1983.
[24] GRS, «Kerntechnischer Ausschuss Statusbericht zum Konzept: Klassifizierung
von Ereignisabläufen für die Auslegung von Kernkraftwerken,» 1985.
[25] C. Queral et al., «Application of Expanded Event Trees combined with uncertainty
analysis methodologies,» Reliab. Eng. Syst. Saf., vol. 205, p. 107246, Jan. 2021.
[26] S. Martorell, F. Sánchez-Sáez, J. F. Villanueva, and S. Carlos, «An extended
BEPU approach integrating probabilistic assumptions on the availability of safety systems
in deterministic safety analyses,» Reliab. Eng. Syst. Saf., 2017.
[27] P. Mazgaj and P. Darnowski, «Demonstration of the E-BEPU Methodology for
LB-LOCA in NPP with PWR Demonstration of the E-BEPU Methodology for LB-LOCA in
NPP with PWR Reactor,» no. September 2020, 2021.
[28] W. N. News, «First European reactor loads EnCore accident tolerant fuel:
Uranium & Fuel - World Nuclear News.» [Online]. Available: https://world-nuclearnews.org/Articles/First-European-reactor-loads-EnCore-accident-toler. [Accessed: 09Dec-2021].
[29] J. Young Kang, T. K. Kim, G. C. Lee, H. J. Jo, M. H. Kim, and H. S. Park, «Impact of
system parameters on quenching heat transfer in the candidate materials for accident tolerant
fuel-cladding in LWRs,» Ann. Nucl. Energy, vol. 129, pp. 375–389, Jul. 2019.
[30] L. Mohanta, F. B. Cheung, S. M. Bajorek, K. Tien, and C. L. Hoxie,
«Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer
grids,» Nucl. Eng. Des., vol. 312, pp. 99–105, 2017.
[31] WGRISK CAPS (2019), Dynamic PSA Methodologies – Preparing for the Future.
[32] J.M. Izquierdo, J. Hortal, M. Sánchez, E. Meléndez; «CSN Experience in the
Development and Application of a Computer Platform to Verify Consistency of
Deterministic and Probabilistic Licensing Safety Cases. Volume I: General Approach and
Deterministic Developments». Consejo de Seguridad Nuclear Colección Otros
Documentos ODE-04-22, CSN 40.2016, Madrid, Spain.
[33] Izquierdo JM; Hortal J, Sanchez-Perea M, Meléndez E.; 2018. The importance
of accident time evolution in regulatory safety assessment. Independent, quantitative
tools and methods at CSN to ensure adequate PSA/DSA applications. CSN publication,
42.2018, Colección «Otros Documentos».
[34] Aldemir T., A survey of dynamic methodologies for probabilistic safety
assessment of nuclear power plants. Annals of Nuclear Energy 52 (2013) 113-124.
[35] Modern Nuclear Energy Analysis Methods Vol.1., Advanced Concepts in
Nuclear Energy Risk Assessment and Management, edited by Tunc Aldemir (The Ohio
State University, USA). June 2018, World Scientific Publishing Co., https://doi.org/
10.1142/10587.
[36] M. Sánchez, R. Mendizábal, F. Pelayo, E. Meléndez, J.M. Izquierdo, J. Hortal,
J. Pérez, «On the role of simulation codes in regulatory activities. Challenges and R&D
needs», Nuclear Engineering and Design 409 (2023) 112345, https://doi.org/10.1016/
j.nucengdes.2023.112345.
[37] Task Group on Safety Margins Action Plan (SMAP) - Final Report. NEA/CSNI/
R(2007)9.
Núm. 3
Miércoles 3 de enero de 2024
Sec. III. Pág. 1097
ANEXO 2
Memoria Económica
1.
Duración del proyecto.
La duración de este proyecto de I+D será de cuatro años.
cve: BOE-A-2024-212
Verificable en https://www.boe.es
[22] M. Dusic, M. Dutton, H. Glaeser, J. Herb, J. Hortal, R. Mendizábal, F. Pelayo,
«Combining insights from probabilistic and deterministic safety analyses in option 4 from
the IAEA specific safety guide SSG-2,» Nucl. Technol., vol. 188, no. 1, pp. 63–77, 2014.
[23] A. N. Society, Ed., ANSI/ANS-51.1-1983 Nuclear Safety Criteria for the Design
of Stationary Pressurized Water Reactor Plants. La Grange Park, Illinois, 1983.
[24] GRS, «Kerntechnischer Ausschuss Statusbericht zum Konzept: Klassifizierung
von Ereignisabläufen für die Auslegung von Kernkraftwerken,» 1985.
[25] C. Queral et al., «Application of Expanded Event Trees combined with uncertainty
analysis methodologies,» Reliab. Eng. Syst. Saf., vol. 205, p. 107246, Jan. 2021.
[26] S. Martorell, F. Sánchez-Sáez, J. F. Villanueva, and S. Carlos, «An extended
BEPU approach integrating probabilistic assumptions on the availability of safety systems
in deterministic safety analyses,» Reliab. Eng. Syst. Saf., 2017.
[27] P. Mazgaj and P. Darnowski, «Demonstration of the E-BEPU Methodology for
LB-LOCA in NPP with PWR Demonstration of the E-BEPU Methodology for LB-LOCA in
NPP with PWR Reactor,» no. September 2020, 2021.
[28] W. N. News, «First European reactor loads EnCore accident tolerant fuel:
Uranium & Fuel - World Nuclear News.» [Online]. Available: https://world-nuclearnews.org/Articles/First-European-reactor-loads-EnCore-accident-toler. [Accessed: 09Dec-2021].
[29] J. Young Kang, T. K. Kim, G. C. Lee, H. J. Jo, M. H. Kim, and H. S. Park, «Impact of
system parameters on quenching heat transfer in the candidate materials for accident tolerant
fuel-cladding in LWRs,» Ann. Nucl. Energy, vol. 129, pp. 375–389, Jul. 2019.
[30] L. Mohanta, F. B. Cheung, S. M. Bajorek, K. Tien, and C. L. Hoxie,
«Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer
grids,» Nucl. Eng. Des., vol. 312, pp. 99–105, 2017.
[31] WGRISK CAPS (2019), Dynamic PSA Methodologies – Preparing for the Future.
[32] J.M. Izquierdo, J. Hortal, M. Sánchez, E. Meléndez; «CSN Experience in the
Development and Application of a Computer Platform to Verify Consistency of
Deterministic and Probabilistic Licensing Safety Cases. Volume I: General Approach and
Deterministic Developments». Consejo de Seguridad Nuclear Colección Otros
Documentos ODE-04-22, CSN 40.2016, Madrid, Spain.
[33] Izquierdo JM; Hortal J, Sanchez-Perea M, Meléndez E.; 2018. The importance
of accident time evolution in regulatory safety assessment. Independent, quantitative
tools and methods at CSN to ensure adequate PSA/DSA applications. CSN publication,
42.2018, Colección «Otros Documentos».
[34] Aldemir T., A survey of dynamic methodologies for probabilistic safety
assessment of nuclear power plants. Annals of Nuclear Energy 52 (2013) 113-124.
[35] Modern Nuclear Energy Analysis Methods Vol.1., Advanced Concepts in
Nuclear Energy Risk Assessment and Management, edited by Tunc Aldemir (The Ohio
State University, USA). June 2018, World Scientific Publishing Co., https://doi.org/
10.1142/10587.
[36] M. Sánchez, R. Mendizábal, F. Pelayo, E. Meléndez, J.M. Izquierdo, J. Hortal,
J. Pérez, «On the role of simulation codes in regulatory activities. Challenges and R&D
needs», Nuclear Engineering and Design 409 (2023) 112345, https://doi.org/10.1016/
j.nucengdes.2023.112345.
[37] Task Group on Safety Margins Action Plan (SMAP) - Final Report. NEA/CSNI/
R(2007)9.
