Zobrazeno 1 - 10
of 37
pro vyhledávání: '"PWR Spent Fuel"'
Autor:
Hong, Jong-Dae a, ⁎, Park, Myungchul a, Holston, Anna-Maria Alvarez b, Stjärnsäter, Johan b, Kook, Donghak a
Publikováno v:
In Journal of Nuclear Materials January 2021 543
Publikováno v:
In Nuclear Engineering and Technology March 2020 52(3):614-620
Autor:
Jang, Jaerim, Kim, Wonkyeong, Jeong, Sanggeol, Jeong, Eun, Park, Jinsu, Lemaire, Matthieu, Lee, Hyunsuk, Jo, Yongmin, Zhang, Peng, Lee, Deokjung ⁎
Publikováno v:
In Annals of Nuclear Energy April 2018 114:495-509
Publikováno v:
In Nuclear Engineering and Design October 2017 322:324-330
Autor:
Ser Gi Hong, Wuseong You
Publikováno v:
Sustainability, Vol 9, Iss 12, p 2225 (2017)
Sustainability; Volume 9; Issue 12; Pages: 2225
Sustainability; Volume 9; Issue 12; Pages: 2225
In this paper, we designed and analyzed advanced sodium-cooled fast reactor cores using uranium-free metallic fuels for maximizing burning rate of transuranics (TRU) nuclides from PWR spent fuels. It is well known that the removal of fertile nuclides
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::30a56d3109f86282171a27b12702d002
https://www.mdpi.com/2071-1050/9/12/2225
https://www.mdpi.com/2071-1050/9/12/2225
Autor:
Eschbach, R., Feng, B., Vezzoni, B., Gabrielli, F., Alvarez-Velarde, F., Leger, V., Rocchi, F., Edwards, G., Dixon, B., Peneliau, Y., Girieud, R., Hakkinen, S., Viitanen, T., Raty, A., Malambu, E., Cornet , S.
Publikováno v:
Eschbach, R, Feng, B, Vezzoni, B, Gabrielli, F, Alvarez-Velarde, F, Léger, V, Rocchi, F, Edwards, G, Dixon, B, Pénéliau, Y, Girieud, R, Häkkinen, S, Viitanen, T, Räty, A, Malambu, E & Cornet, S 2017, ' Verification of dose rate calculations for PWR spent fuel assemblies ', Paper presented at GLOBAL 2017, International Nuclear Fuel Cycle Conference, Seoul, Korea, Republic of, 24/09/17-29/09/17 .
GLOBAL 2017-International Nuclear Fuel Cycle Conference
GLOBAL 2017-International Nuclear Fuel Cycle Conference, Sep 2017, Seoul, South Korea
GLOBAL 2017-International Nuclear Fuel Cycle Conference
GLOBAL 2017-International Nuclear Fuel Cycle Conference, Sep 2017, Seoul, South Korea
International audience; Under the framework of the Nuclear Energy Agency's Expert Group on Advanced Fuel Cycle Scenarios (NEA/AFCS), a benchmark on dose rate calculations for Pressurized Water Reactor (PWR) Spent Fuel Assembly is currently underway.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::ea9dbe3419f4b80153b8f9ccff777bcc
https://cris.vtt.fi/en/publications/82a01842-c98b-4718-98cc-c7bc521a1411
https://cris.vtt.fi/en/publications/82a01842-c98b-4718-98cc-c7bc521a1411
Publikováno v:
Nuclear Technology. 149(1):1-13
Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent nuclear fuel repository facilities for the Slovenian nuclear power plant Krsko are presented. The MCNP4C code was deployed to model and assess the ne
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dris___01423::3d339e6732274fe0da86cf7c3da7c290
https://research.rug.nl/en/publications/257f18cf-4868-4703-9bf6-d8c733e449b5
https://research.rug.nl/en/publications/257f18cf-4868-4703-9bf6-d8c733e449b5
Autor:
Marko Maucec, Bogdan Glumac
Publikováno v:
Nuclear Technology, 149(1), 1-13
Monte Carlo criticality safety and sensitivity calcu- lations of pressurized water reactor (PWR) spent nuclear fuel repository facilities for the Slovenian nuclear power plant Krsko are presented. The MCNP4C code was de- ployed to model and assess th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::50cb2ccdd58a9fc0c7169c42c4dd2085
https://doi.org/10.13182/nt05-a3575
https://doi.org/10.13182/nt05-a3575
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Akademický článek
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