Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Generation IV, supercritical water reactor"'
Publikováno v:
Penttilä, S, Rissanen, L, Saario, T & Toivonen, A 2011, Corrosion and creep studies of candidate in-core materials for Generation IV supercritical water reactor . in Proceedings of the 2nd international conference on advances in nuclear materials : Abstract booklet and souvenir . Bhabha Atomic Research Centre (BARC), Mumbai, 2nd International Conference on Advances in Nuclear Materials, ANM 2011, Mumbai, India, 9/02/11 .
The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; HPLWR uses supercritical water as coolant with design reactor outlet temperature at about 500 °C. The out-of-core material choices can
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::f241eac696a2fda0ee608c19c9a7bfb3
https://cris.vtt.fi/en/publications/9f8b84c6-0184-44f6-bae5-8efab19f098d
https://cris.vtt.fi/en/publications/9f8b84c6-0184-44f6-bae5-8efab19f098d
The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; HPLWR uses supercritical water as coolant with design reactor outlet temperature at about 500 °C. The out-of-core material choices can
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dris___01229::45c1b913c65a1aa8214e118482d7713d
https://cris.vtt.fi/en/publications/9f8b84c6-0184-44f6-bae5-8efab19f098d
https://cris.vtt.fi/en/publications/9f8b84c6-0184-44f6-bae5-8efab19f098d
Autor:
Seppälä, Malla
Publikováno v:
Seppälä, M 2008, ' Neutronic and Thermal-hydraulic Modelling of High Performance Light Water Reactor : Master's thesis ', Master Degree, Helsinki University of Technology, Espoo . < http://www.vtt.fi/inf/julkaisut/muut/2008/HPLRW-Seppala.pdf >
High Performance Light Water Reactor (HPLWR) is a new reactor concept that operates at supercritical pressure conditions. VTT participates in the 'HPLWR2' project, in which the technological feasibility and economical competitiveness of the concept a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::937a64bdc202f3ff10598f22c688f1c6
https://cris.vtt.fi/en/publications/ad89a967-fe06-4b0a-98e9-3c69468ae74f
https://cris.vtt.fi/en/publications/ad89a967-fe06-4b0a-98e9-3c69468ae74f
Publikováno v:
Materials & Corrosion / Werkstoffe und Korrosion; Jan2019, Vol. 70 Issue 1, p48-56, 9p
Autor:
Elmanakhly, Faris1, DaCosta, Andre2, Berry, Brittany3,4, Stasko, Robert4, Fowler, Michael2, Xiao-Yu Wu1 xiaoyu.wu@uwaterloo.ca
Publikováno v:
AIMS Energy. 2021, Vol. 9 Issue 4, p775-811. 37p.
Autor:
Bischoff, Jeremy bischoff.jeremy@gmail.com, Motta, Arthur T.1
Publikováno v:
Journal of Nuclear Materials. May2012, Vol. 424 Issue 1-3, p261-276. 16p.
Autor:
Espinosa–Martínez, E. -G., Martin-del-Campo, C., Francois, J. L., Quezada–García, S., Vázquez-Rodríguez, A., Espinosa-Paredes, G.
Publikováno v:
Proceedings of The 20th Pacific Basin Nuclear Conference; 2017, p239-252, 14p
Publikováno v:
JOM: The Journal of The Minerals, Metals & Materials Society (TMS); Jul2015, Vol. 67 Issue 7, p1420-1430, 11p, 35 Color Photographs
Publikováno v:
MRS Online Proceedings Library; 2008, Vol. 1125 Issue 1, p1-6, 6p
Publikováno v:
Li, J, Liu, P, Zavadil, R, Malis, T & Penttilä, S 2014, ' Effect of surface modification on candidate alloys for canadian SCWR fuel cladding ', Journal of Minerals and Materials Characterization and Engineering, vol. 2, no. 2, pp. 129-134 . https://doi.org/10.4236/jmmce.2014.22017
The Canadian Generation-IV supercritical water reactor (SCWR) requires peak cladding surface temperature of 800? for a core outlet temperature of 625[Celcius]. Materials selection for high temperature fuel cladding is becoming one of the major challe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0002edef9889361df38871478252757d
https://doi.org/10.4236/jmmce.2014.22017
https://doi.org/10.4236/jmmce.2014.22017