المؤلفون: Tenglong Cong, Hao Chen, Chao Chen, Shaohong Zhang, Hanyang Gu

المصدر: International Journal of Advanced Nuclear Reactor Design and Technology, Vol 4, Iss 3, Pp 129-138 (2022)

مصطلحات موضوعية: Fuel performance analysis code, FuSPAC, Fuel behaviour under irradiation, UO2 fuel, Nuclear engineering. Atomic power, TK9001-9401

وصف الملف: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S246860502200028X; https://doaj.org/toc/2468-6050

URL الوصول: https://doaj.org/article/dd0d073d3d6f416bb80395fca246de52

المؤلفون: Arce, María Elena

المصدر: Energy, Sustainability and Society. December 2015 5(1):1-10

لا يتم عرض هذه النتيجة على الضيوف.
تسجيل الدخول للوصول الكامل.

لا يتم عرض هذه النتيجة على الضيوف.
تسجيل الدخول للوصول الكامل.

المؤلفون: A. Gallais-During, J. Lamontagne, C. Le Gall, E. Hanus, G. Ducros, E. Geiger, Yves Pontillon

المساهمون: CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)

المصدر: Journal of Nuclear Materials
Journal of Nuclear Materials, 2017, 495, pp.49-57. ⟨10.1016/j.jnucmat.2017.08.002⟩

مصطلحات موضوعية: Fuel-cladding interactions, Nuclear and High Energy Physics, [PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th], Nuclear engineering, Sample (statistics), 02 engineering and technology, [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], Experimental laboratory, 01 natural sciences, 010305 fluids & plasmas, 0103 physical sciences, General Materials Science, Light-water reactor, LWR, Fuel behaviour, Severe accident, Fission products, VERDON tests, Nuclear fuel, Radioactive waste, Post-test characterisations, 021001 nanoscience & nanotechnology, ISTP, Nuclear Energy and Engineering, UO2 irradiated fuel, Environmental science, 0210 nano-technology, Nuclear chemistry

URL الوصول: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::afb9e8e5eef9e147b4e8e2d6b815e237
https://doi.org/10.1016/j.jnucmat.2017.08.002

المؤلفون: Gerhard Bart, Johannes Bertsch

المصدر: CHIMIA, Vol 59, Iss 12 (2005)

مصطلحات موضوعية: Cladding corrosion, Fuel behaviour, Lwr, Chemistry, QD1-999

وصف الملف: electronic resource

Relation: https://chimia.ch/chimia/article/view/4095; https://doaj.org/toc/0009-4293; https://doaj.org/toc/2673-2424

URL الوصول: https://doaj.org/article/b4d9fea661da42a485e3f7bc3eca48e5

المؤلفون: Loukusa, Henri, Peltonen, Jussi, Valtavirta, Ville

المصدر: Loukusa, H, Peltonen, J & Valtavirta, V 2019, FINIX-Fuel behavior model and interface for multiphysics applications-Code documentation for version 1.19.1 . VTT Research Report, no. VTT-R-00052-19, VTT Technical Research Centre of Finland .

مصطلحات موضوعية: FINIX, fuel behaviour modelling

وصف الملف: application/pdf

URL الوصول: https://explore.openaire.eu/search/publication?articleId=355e65625b88::a6db9798aa6862f9a3dbc9eef726c086
https://cris.vtt.fi/en/publications/66007d54-6c57-4d41-a1ea-3c1462daa0fc

مصطلحات موضوعية: FINIX, fuel behaviour modelling

URL الوصول: https://explore.openaire.eu/search/publication?articleId=dris___01229::772935059cdcdb96d89419d2921dd2ff
https://cris.vtt.fi/en/publications/66007d54-6c57-4d41-a1ea-3c1462daa0fc

المؤلفون: Mitev, M., Mihaylov, N.

مصطلحات موضوعية: Design based accidents, Dosimetry planning, Radioactivity release, Fuel behaviour

URL الوصول: https://explore.openaire.eu/search/publication?articleId=doi_________::f8cafce7394848156553211ed5ab9b41

المؤلفون: A. Schubert, Ville Rintala, Paul Van Uffelen, Heikki Suikkanen

المساهمون: Lappeenrannan-Lahden teknillinen yliopisto LUT, Lappeenranta-Lahti University of Technology LUT, fi=School of Energy Systems|en=School of Energy Systems

المصدر: Nuclear Engineering and Design. 359:110450

مصطلحات موضوعية: Nuclear and High Energy Physics, Neutron transport, 020209 energy, Nuclear engineering, Serpent (cipher), Monte Carlo method, 02 engineering and technology, 01 natural sciences, 010305 fluids & plasmas, Neutron flux, 0103 physical sciences, 0202 electrical engineering, electronic engineering, information engineering, Burnup calculation, General Materials Science, Fuel behaviour, Safety, Risk, Reliability and Quality, Waste Management and Disposal, Power density, Physics, Thermo-mechanics, Mechanical Engineering, Solver, Coupled calculation, Nuclear Energy and Engineering, Data exchange, Monte Carlo neutronics, Reactor physics

وصف الملف: fulltext

URL الوصول: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::60bb7e613193d426aaaf2defa0956201
https://doi.org/10.1016/j.nucengdes.2019.110450