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在“Elsevier电子期刊”中，命中：15条，耗时：0.0139985 秒

1.Development, verification, and validation of a fuel thermal conductivity degradation model in CTF

作者：Mine O. Yilmaz^a ; ^{ozdemirmine@hotmail.com" class="auth_mail" title="E-mail the corresponding author} ; Maria N. Avramova^b ; ^{mnavramo@ncsu.edu" class="auth_mail" title="E-mail the corresponding author} ; Jens G.M. Andersen^c ; ^{jandersen@ec.rr.com" class="auth_mail" title="E-mail the corresponding author}

关键词：Fuel thermal conductivity ; Fuel centerline temperature ; CTF ; FRAPCON-3.4

刊名：Annals of Nuclear Energy

出版年：2016

2.Thermal-mechanical performance modeling of thorium-plutonium oxide fuel and comparison with on-line irradiation data

作者：Klara Insulander Bjö ; rk^a ; ^b ; ^{klara.insulander@scatec.no" class="auth_mail" title="E-mail the corresponding author} ; Laura Kekkonen^c ; ^d

关键词：Nuclear fuel ; Thermal&ndash ; mechanical performance ; FRAPCON ; Thorium ; Plutonium

刊名：Journal of Nuclear Materials

出版年：2015

3.Application of advanced validation concepts to oxide fuel performance codes: LIFE-4 fast-reactor and FRAPCON thermal-reactor fuel performance codes

作者：C. Unal ; B.J. Williams ; A. Yacout ; D.M. Higdon

关键词：AISI ; American Iron and Steel Institute ; EBR-II ; Experimental Breeder Reactor-II ; FCAS ; fuel column axial strain ; FCHR ; fuel central hole radius ; FCMI ; fuel cladding mechanical interaction ; FCZR ; fuel column zone radius ; FEZR ; fuel equiaxed zone radius ; F

刊名：Nuclear Engineering and Design

出版年：2013

4.Calibration of tuning parameters in the FRAPCON model

作者：Dave Higdon^a ; ^{dhigdon@lanl.gov} ; Ken Geelhood^b ; Brian Williams^a ; Cetin Unal^a

关键词：Parameter estimation ; Computer experiments ; Prediction ; Uncertainty quantification ; Gaussian process

刊名：Annals of Nuclear Energy

出版年：2013

5.Effects of pellet-to-cladding gap design parameters on the reliability of high burnup PWR fuel rods under steady state and transient conditions

作者：Fatma Burcu Tas^a ; ^{burcutas@ktu.edu.tr} ; Sule Ergun^b

关键词：Nuclear fuel reliability ; Fuel behavior ; High burnup ; Pellet&ndash ; cladding gap ; FRAPCON-3.4a ; FRAPTRAN-1.4

刊名：Energy Conversion and Management

出版年：2013

6.Steady-state fuel behavior modeling of nitride fuels in FRAPCON-EP

作者：Bo Feng ; Ayd?n Karahan ; Mujid S. Kazimi

关键词：TD ; theoretical density ; HM ; heavy metal ; FGR ; fission gas release ; BOC ; beginning-of-cycle ; MOC ; middle-of-cycle ; EOC ; end-of-cycle ; LOCA ; Loss of Coolant Accident ; SD ; standard deviation ; AE ; average fractional error ; EOL ; end-of-life

刊名：Journal of Nuclear Materials

出版年：2012

7.Visualization of fuel rod burnup analysis by Scilab

作者：Chiung-Wen Tsai

刊名：Nuclear Engineering and Design

出版年：December, 2013

8.Extension of the FRAPCON-3.3 creep model to dry storage conditions

作者：L.E. Herranz ; F. Feria

关键词：Model ; Fuel rod creep ; Dry storage

刊名：Progress in Nuclear Energy

出版年：2010

9.Effects of edge dislocations on thermal transport in UO₂

作者：B. Deng ; A. Chernatynskiy ; P. Shukla ; S.B. Sinnott ; S.R. Phillpot ; ^{sphil@mse.ufl.edu}

刊名：Journal of Nuclear Materials

出版年：2013

10.Creep assessment of Zry-4 cladded high burnup fuel under dry storage

作者：F. Feria ; ^a ; ^{francisco.feria@ciemat.es} ; L.E. Herranz^a

关键词：Fuel rod ; Creep ; Dry storage

刊名：Progress in Nuclear Energy

出版年：2011

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