يعرض 1 - 10 نتائج من 2,542 نتيجة بحث عن '"Decay heat"', وقت الاستعلام: 1.18s تنقيح النتائج
  1. 1
    دورية أكاديمية
    Concepts of heat dissipation of a disposal canister and its computational analysis

    المؤلفون: Minseop Kim, Minsoo Lee, Jinseop Kim, Seok Yoon

    المصدر: Nuclear Engineering and Technology, Vol 55, Iss 11, Pp 4173-4180 (2023)

    مصطلحات موضوعية: Bentonite buffer, Disposal canister, Decay heat, Heat dissipation, Heat transfer, Copper, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    العلاقة: http://www.sciencedirect.com/science/article/pii/S1738573323003558Test; https://doaj.org/toc/1738-5733Test

    الوصول الحر: https://doaj.org/article/00200c544fd9423b8f26ea0b5a62a7cbTest

    View record in DOAJ النص الكامل

    أضف إلى المفضلة
  2. 2
    دورية أكاديمية
    Überarbeitete Analyse des PUIREX 2008 Nachzerfallswärmeexperiments im schnelle Reaktor Phénix ; Revisited analysis of the PUIREX 2008 decay heat experiment in the Phénix Sodium Fast Reactor ; Analyse revisitée de l'expérience de puissance résiduelle PUIREX 2008 dans le Réacteur à Neutrons Rapides Phénix

    المؤلفون: da Cunha, Dorian, Nguyen, Frédéric, Lebrat, Jean-François, Le Niliot, Christophe

    المساهمون: Institut de recherche sur les systèmes nucléaires pour la production d'énergie bas carbone (CEA - DES) (IRESNE), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut universitaire des systèmes thermiques industriels (IUSTI), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS)

    المصدر: ISSN: 0306-4549 ; Annals of Nuclear Energy ; https://hal.science/hal-04581573Test ; Annals of Nuclear Energy, 2024, 205, pp.110537. ⟨10.1016/j.anucene.2024.110537⟩.

    مصطلحات موضوعية: Decay heat, Sodium Fast Reactor, Phénix, Experiment, Validation, Uncertainty, Puissance résiduelle, Réacteurs à Neutrons Rapides, Expérience, Incertitude, [PHYS]Physics [physics]

    العلاقة: hal-04581573; https://hal.science/hal-04581573Test; https://hal.science/hal-04581573/documentTest; https://hal.science/hal-04581573/file/1-s2.0-S0306454924002007-main.pdfTest

    الإتاحة: https://doi.org/10.1016/j.anucene.2024.110537Test
    https://hal.science/hal-04581573Test
    https://hal.science/hal-04581573/documentTest
    https://hal.science/hal-04581573/file/1-s2.0-S0306454924002007-main.pdfTest

    View record in BASE

    أضف إلى المفضلة
  3. 3
    دورية أكاديمية
    Fade-out time shortening on radiotoxicity and decay heat using TRU generation reduction fuel

    المؤلفون: Kouji HIRAIWA, Rei KIMURA, Satoshi WADA, Tsukasa SUGITA, Kenichi YOSHIOKA, Satoshi TAKEDA, Takanori KITADA

    المصدر: Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00381-23-00381 (2023)

    مصطلحات موضوعية: trans uranium (tru), radiotoxicity, high level waste (hlw), spent nuclear fuel (snf), decay heat, high assay low enriched uranium (haleu), advanced boiling water reactor (abwr), partitioning and transmutation (p&t), fission product (fp), Mechanical engineering and machinery, TJ1-1570

    وصف الملف: electronic resource

    العلاقة: https://www.jstage.jst.go.jp/article/mej/11/2/11_23-00381/_pdf/-char/enTest; https://doaj.org/toc/2187-9745Test

    الوصول الحر: https://doaj.org/article/6e095515c6ee4db29c7265a1c7df660cTest

    View record in DOAJ

    أضف إلى المفضلة
  4. 4
    Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat

    المؤلفون: Jansson, Peter, Bengtsson, Martin, Bäckström, Ulrika, Álvarez-Velarde, Francisco, Čalič, Dušan, Stefano, Caruso, Ron, Dagan, Fiorito, Luca, Lydie, Giot, Govers, Kevin, Hernandez Solis, Augusto, Hannstein, Volker, Ilas, Germina, Kromar, Marjan, Leppänen, Jaakko, Mosconi, Marita, Ortego, Pedro, Plukienė, Rita, Plukis, Arturas, Ranta-aho, Anssu, Rochman, Dimitri, Ros, Linus, Sato, Shunsuke, Schillebeeckx, Peter, Shama, Ahmed, Simeonov, Teodosi, Stankovskiy, Alexey, Trellue, Holly, Vaccaro, Stefano, Vallet, Vanessa, Marc, Verwerft, Žerovnik, Gašper, Sjöland, Anders

    المصدر: Nuclear science and engineering. 196(9):1125-1145

    مصطلحات موضوعية: Spent nuclear fuel, decay heat, calorimeter, experimental measure, validation, Fysik med inriktning mot tillämpad kärnfysik, Physics with specialization in Applied Nuclear Physics

    وصف الملف: electronic

    الوصول الحر: https://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-455329Test
    https://doi.org/10.1080/00295639.2022.2053489Test
    https://uu.diva-portal.org/smash/get/diva2:1600858/FULLTEXT01.pdfTest

    View record in SwePub

    أضف إلى المفضلة
  5. 5
    دورية أكاديمية
    Study on Inherent Safety Characteristic on Thermal-hydraulic of Pool-type Sodium-cooled Fast Reactors

    المؤلفون: ZHOU Zhiwei;XUE Xiuli;YANG Yong;YANG Hongyi

    المصدر: Yuanzineng kexue jishu, Vol 57, Iss 7, Pp 1397-1405 (2023)

    مصطلحات موضوعية: sodium-cooled fast reactor, natural circulation, passive decay heat removal, inherent safety, thermal inertia, thermal-hydraulic safety characteristic, Nuclear engineering. Atomic power, TK9001-9401, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798

    وصف الملف: electronic resource

    العلاقة: https://www.aest.org.cn/EN/abstract/abstract21827.shtmlTest; https://doaj.org/toc/1000-6931Test

    الوصول الحر: https://doaj.org/article/d5ffae4f94f449739844e70149ba0bc8Test

    View record in DOAJ

    أضف إلى المفضلة
  6. 6
    دورية أكاديمية
    Analysis of fission product source term release and decay heat under pressurized water reactor rupture accident

    المؤلفون: YUAN Xianbao, PENG Jueqin, ZHANG Binhang, MAO Zhangliang, TANG Haibo, WEI Jingyu, ZHOU Jianjun

    المصدر: He jishu, Vol 47, Iss 4, Pp 040603-040603 (2024)

    مصطلحات موضوعية: breaching accident, fission product source term, failed containment, spray system, decay heat, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    العلاقة: http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2024.hjs.47.040603&lang=zhTest; https://doaj.org/toc/0253-3219Test

    الوصول الحر: https://doaj.org/article/245769fdc84e4d35af0bcd8b01413a9aTest

    View record in DOAJ

    أضف إلى المفضلة
  7. 7
    دورية أكاديمية
    High-efficiency deep geological repository system for spent nuclear fuel in Korea with optimized decay heat in a disposal canister and increased thermal limit of bentonite

    المؤلفون: Jongyoul Lee, Kwangil Kim, Inyoung Kim, Heejae Ju, Jongtae Jeong, Changsoo Lee, Jung-Woo Kim, Dongkeun Cho

    المصدر: Nuclear Engineering and Technology, Vol 55, Iss 4, Pp 1540-1554 (2023)

    مصطلحات موضوعية: Spent nuclear fuel, Deep geological disposal, Design requirements, High efficiency, Optimized decay heat, Thermal limits, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    العلاقة: http://www.sciencedirect.com/science/article/pii/S1738573323001031Test; https://doaj.org/toc/1738-5733Test

    الوصول الحر: https://doaj.org/article/9a53a07357e7487f97f4e873a2f01e7aTest

    View record in DOAJ النص الكامل

    أضف إلى المفضلة
  8. 8
    دورية أكاديمية
    Dataset of observables for UOX and MOX spent fuel extracted from Serpent2 fuel depletion calculations for PWRs

    المؤلفون: Victor J. Casas-Molina, Augusto Hernandez-Solis, Pablo Romojaro, Ivan Merino-Rodríguez, Nerea Aguilera-Gómez

    المصدر: Data in Brief, Vol 49, Iss , Pp 109412- (2023)

    مصطلحات موضوعية: Spent nuclear fuel, UOX, MOX, Nuclide inventory, Decay heat, Neutron and gamma emission, Computer applications to medicine. Medical informatics, R858-859.7, Science (General), Q1-390

    وصف الملف: electronic resource

    العلاقة: http://www.sciencedirect.com/science/article/pii/S2352340923005140Test; https://doaj.org/toc/2352-3409Test

    الوصول الحر: https://doaj.org/article/b5c7ca16ad3145eab69fdc101cce02c6Test

    View record in DOAJ النص الكامل

    أضف إلى المفضلة
  9. 9
    دورية أكاديمية
    Analysis on short-term decay heat after shutdown during load-follow operation with seasonal and daily scenarios

    المؤلفون: Dae Hee Hwang, Yonghee Kim

    المصدر: Nuclear Engineering and Technology, Vol 54, Iss 10, Pp 3878-3887 (2022)

    مصطلحات موضوعية: Load-follow operation, Short-term decay heat, Accumulated decay heat, Nuclide-wise decomposition, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    العلاقة: http://www.sciencedirect.com/science/article/pii/S1738573322002522Test; https://doaj.org/toc/1738-5733Test

    الوصول الحر: https://doaj.org/article/125a4fe34b8d458caf02fea485c1d64cTest

    View record in DOAJ النص الكامل

    أضف إلى المفضلة
  10. 10
    دورية أكاديمية
    Spent fuel characterization analysis using various nuclear data libraries

    المؤلفون: Dušan Čalič, Marjan Kromar

    المصدر: Nuclear Engineering and Technology, Vol 54, Iss 9, Pp 3260-3271 (2022)

    مصطلحات موضوعية: Spent nuclear fuel, Decay heat, Serpent, Monte Carlo, Nuclide uncertainties, Nuclear engineering. Atomic power, TK9001-9401

    وصف الملف: electronic resource

    العلاقة: http://www.sciencedirect.com/science/article/pii/S1738573322002121Test; https://doaj.org/toc/1738-5733Test

    الوصول الحر: https://doaj.org/article/a063ef410b8f4aaebf9e26c40e46203bTest

    View record in DOAJ النص الكامل

    أضف إلى المفضلة
أدوات البحث: أحصل على تغذية RSS — أرسل هذا البحث بالبريد الإلكتروني — حفظ البحث