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Neutron cross-sections for next generation reactors: New data from n_TOF
Neutron cross-sections for next generation reactors: New data from n_TOF
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Neutron cross-sections for next generation reactors: New data from n_TOF

Colonna, N. ; Abbondanno, U. ; Aerts, G. ; Álvarez, H. ; Álvarez-Velarde, F. ; Andriamonje, S. ; Andrzejewski, J. ; Assimakopoulos, P. ; Audouin, L. ; Badurek, G. ; Becvar, F. ; Berthoumieux, E. ; Calviani, M. ; Calviño, F. ; Cano-Ott, D. ; Capote, R. ; Carrillo de Albornoz, A. ; Chepel, V. ; Chiaveri, E. ; Cortes, G. ; Cox, J. ; Dahlfors, M. ; David, S. ; Dillman, I. ; Dolfini, R. ; Domingo-Pardo, C. ; Duran, I. ; Eleftheriadis, C. ; Ferrant, L. ; Ferrari, A. ; Ferreira-Marques, R. ; Frais-Koelbl, H. ; González-Romero, E. ; Goverdovski, A. ; Griesmayer, E. ; Guerrero, C. ; Haas, B. ; Haight, R. ; Heil, M. ; Herrera-Martinez, A. ; Igashira, M. ; Isaev, S. ; Jericha, E. ; Käppeler, F. ; Kadi, Y. ; Karadimos, D. ; Ketlerov, V. ; Koehler, P. ; Konovalov, V. ; Kossionides, E. ; Krticka, M. ; Leeb, H. ; Lindote, A. ; Lopes, I. ; Lukic, S. ; Marganiec, J. ; Marrone, S. ; Martínez, T. ; Massimi, C. ; Mastinu, P. ; Mengoni, A. ; Milazzo, P.M. ; Moreau, C. ; Mosconi, M. ; Oberhummer, H. ; O’Brien, S. ; Oshima, M. ; Papachristodoulou, C. ; Papadopoulos, C. ; Paradela, C. ; Pavlik, A. ; Pavlopoulos, P. ; Perrot, L. ; Pigni, M.T. ; Plag, R. ; Plompen, A. ; Plukis, A. ; Poch, A. ; Pretel, C. ; Quesada, J. ; Rauscher, T. ; Reifarth, R. ; Rosetti, M. ; Rubbia, C. ; Rudolf, G. ; Rullhusen, P. ; Salgado, J. ; Stephan, C. ; Tagliente, G. ; Tassan-Got, L. ; Tavora, L. ; Vaz, P. ; Villamarin, D. ; Vicente, M.C. ; Vlachoudis, V. ; Vlastou, R. ; Walter, S. ; Wendler, H. ; Wiescher, M. ; Wisshak, K.

Applied radiation and isotopes, 2010-04, Vol.68 (4), p.643-646 [Periódico revisado por pares]

England: Elsevier Ltd

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2
RITM-200: new-generation reactor for a new nuclear icebreaker
RITM-200: new-generation reactor for a new nuclear icebreaker
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RITM-200: new-generation reactor for a new nuclear icebreaker

Zverev, D. L. ; Pakhomov, A. N. ; Polunichev, V. I. ; Veshnyakov, K. B. ; Kabin, S. V.

Atomic energy (New York, N.Y.), 2013-04, Vol.113 (6), p.404-409 [Periódico revisado por pares]

Boston: Springer US

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3
Development of canisters for spent fuels of VVER-1200 and ATMEA1 new generation reactors and determination of geological disposal densities
Development of canisters for spent fuels of VVER-1200 and ATMEA1 new generation reactors and determination of geological disposal densities
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Development of canisters for spent fuels of VVER-1200 and ATMEA1 new generation reactors and determination of geological disposal densities

Özeşme, Gürel ; Bulut Acar, Banu

Annals of nuclear energy, 2021-01, Vol.150, p.107860, Article 107860 [Periódico revisado por pares]

Elsevier Ltd

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4
Revising the Emergency Management Requirements for new generation reactors
Revising the Emergency Management Requirements for new generation reactors
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Revising the Emergency Management Requirements for new generation reactors

Mancini, Federica C.V. ; Gallego, Eduardo ; Ricotti, Marco E.

Progress in nuclear energy (New series), 2014-03, Vol.71, p.160-171 [Periódico revisado por pares]

Elsevier Ltd

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5
Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities
Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities
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Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities

Joshi, K. A. ; Poudel, B. ; Gokaraju, R.

Journal of nuclear engineering and radiation science, 2020-04, Vol.6 (2) [Periódico revisado por pares]

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6
Human Factors Engineering in the Design of the Socio-Technical System of the Control Room of a New Generation Reactor: Issues Faced During Multistage Validation
Human Factors Engineering in the Design of the Socio-Technical System of the Control Room of a New Generation Reactor: Issues Faced During Multistage Validation
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Human Factors Engineering in the Design of the Socio-Technical System of the Control Room of a New Generation Reactor: Issues Faced During Multistage Validation

Couix, Stanislas

Nuclear technology, 2018-06, Vol.202 (2-3), p.290-298 [Periódico revisado por pares]

La Grange Park: Taylor & Francis

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7
Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors
Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors
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Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors

Tan, L. ; Snead, L.L. ; Katoh, Y.

Journal of nuclear materials, 2016-09, Vol.478, p.42-49 [Periódico revisado por pares]

Elsevier B.V

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8
Investigation of the properties of the nuclei used on the new generation reactor technology systems
Investigation of the properties of the nuclei used on the new generation reactor technology systems
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Investigation of the properties of the nuclei used on the new generation reactor technology systems

Tel, Eyyup ; Şahin, Hacı Mehmet ; Kaplan, Abdullah ; Aydin, Abdullah ; Altınok, Taner

Annals of nuclear energy, 2008-02, Vol.35 (2), p.220-227 [Periódico revisado por pares]

Elsevier Ltd

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9
Optimization and burnup calculations of BNPP's reactor core with the new generation fuels (TVS-2M) by artificial neural network
Optimization and burnup calculations of BNPP's reactor core with the new generation fuels (TVS-2M) by artificial neural network
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Optimization and burnup calculations of BNPP's reactor core with the new generation fuels (TVS-2M) by artificial neural network

Afzali, Milad ; Allaf, Mitra Athari ; Jahanfarnia, Gholamreza ; Kheradmand, Mohsen

Progress in nuclear energy (New series), 2022-08, Vol.150, p.104290, Article 104290 [Periódico revisado por pares]

Elsevier Ltd

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10
Neutronic-thermal hydraulic coupling analysis of the fuel channel of a new generation of the small modular pressurized water reactor including hexagonal and square fuel assemblies using MCNP and CFX
Neutronic-thermal hydraulic coupling analysis of the fuel channel of a new generation of the small modular pressurized water reactor including hexagonal and square fuel assemblies using MCNP and CFX
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Neutronic-thermal hydraulic coupling analysis of the fuel channel of a new generation of the small modular pressurized water reactor including hexagonal and square fuel assemblies using MCNP and CFX

Erfaninia, Ali ; Hedayat, Afshin ; Mirvakili, S.M. ; Nematollahi, M.R.

Progress in nuclear energy (New series), 2017-07, Vol.98, p.213-227 [Periódico revisado por pares]

Oxford: Elsevier Ltd

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