.... , Haskin , T. C. , and Corradini , M. L. , 2017 , “ Accident Tolerant Clad Material Modeling by MELCOR: Benchmark for SURRY Short Term Station Blackout ,” Nucl. Eng. Des. , 313 , pp. 458 – 469 . 10.1016/j.nucengdes.2017.01.002 [6] Wang , J. , Jo , H. J. , and Corradini , M. L...

... as Plasma Facing Material ,” J. Nucl. Mater. , 155 , pp. 49 – 57 . 10.1016/0022-3115(88)90226-7 [2] Pimenta , M. , Dresselhaus , G. , Dresselhaus , M. S. , Cancado , L. , Jorio , A. , and Saito , R. , 2007 , “ Studying Disorder in Graphite-Based Systems by Raman...

..., 2017; final manuscript received April 5, 2018; published online September 10, 2018. Assoc. Editor: Akos Horvath. 26 10 2017 05 04 2018 Current reactors Nuclear fuels Nuclear safety Radiation protection Materials Security Radiation science Nuclear reactor pressure...

... received September 27, 2017; final manuscript received May 22, 2018; published online September 10, 2018. Editor: Igor Pioro. 27 09 2017 22 05 2018 Next generation reactors Nuclear fuels Materials Selection of appropriate materials able to work for a long time in contact...

... Radioactive waste management Decommissioning Materials The management of long-lived radioactive production in the spent nuclear fuel is one of the most difficult issues associated with nuclear power generation. One of the concepts for dealing with the long-lived isotopes, the so-called open cycle...

...Muhammad Qasim Awan; Liangzhi Cao; Hongchun Wu; Chuanqi Zhao Use of FCM fuel in light water reactors is an attractive option for existing and future generations of these reactors to make them accident tolerant in nature. This work focuses on the neutronic study of the use of burnable material...

... , Aluminum 6063 , Aluminum 1100 , control rod poison, mild steel, and SS-304 definitions used in the models were based on definitions from Tables 3.5, 3.17, 3.15, 3.21, 3.18, and 3.19 of [ 1 ], respectively. The two materials with the highest impact on the k-eff are naturally the fuel...

... Materials in Pb-Bi Eutectic at Temperatures 400-600 °C ,” Corros. Sci. , 48 ( 3 ), pp. 577 – 594 . 10.1016/j.corsci.2005.04.001 [13] Aiello , A. , Azzati , M. , Benamati , G. , Gessi , A. , Long , B. , and Scaddozzo , G. , 2004 , “ Corrosion Behaviour of Stainless Steels...

.... It is speculated that uranium and zirconium oxide solid solution (U,Zr)O 2 is one of the major materials in the fuel debris from 1F. In addition, the Zr content of the fuel debris from 1F is expected to be higher than that of the debris from TMI-2 because the 1F reactors were boiling-water reactors...

... a reduction in the centerline temperature and temperature gradient in dispersed fuels but also reveals the maximum concentration of fissile material (U 3 O 8 , U 3 Si 2 , and UN) that can be incorporated in the Al matrix without the centerline melting. Furthermore, these predictions enable the experimental...

... of the mechanism of the fission gas atoms migration in UO 2 fuel from an atomic level. Nuclear fuels Materials 31 10 2017 20 03 2018 Manuscript received October 31, 2017; final manuscript received March 20, 2018; published online May 16, 2018. Assoc. Editor: Akos Horvath. 1...

... and the irradiation creeps of the cladding material, the gap heat transfer, are adequately taken into account. The module is implemented within the general-purpose finite element code, i.e., abaqus , through writing user subroutines. The paper first introduces the constitutive models for fuel and cladding materials...

.... Manuscript received December 9, 2016; final manuscript received June 10, 2017; published online March 5, 2018. Assoc. Editor: Michal Kostal. 09 12 2016 10 06 2017 Design-basis event Nuclear fuels Nuclear safety Materials Security The Chernobyl and Fukushima accidents...

...; the gas conductance and radiant conductance of gap heat transfer were considered, the forced convective heat transfer on the outer surface of cladding was considered. Meanwhile, the irradiation effects and the thermal effects on the materials parameters such as thermal conductivity, specific heat...

... a core outlet temperature of 650 °C at 25 MPa and a peak cladding temperature as high as 800 °C. Corrosion/oxidation resistance is an important factor in material selections and also coating considerations. Most of the reported supercritical water (SCW) test data have been obtained at temperatures up...

... on the surface after 300 and 600 h of exposure. However, as exposure progressed, more Ni and Mn-containing spinel started to form, signaling Cr and Al depletion on the metal substrate surface. Next generation reactors Nuclear fuels Materials Concerns with greenhouse gas emissions and uncertainty...

... 06 2017 Nuclear fuels Materials Uranium dioxide (UO 2 ) is the most widely used nuclear fuel for commercial light water thermal reactor due to its excellent performances such as high melting point, good dimensional and radiation stability, and outstanding chemical compatibility...

... Laboratory, Oak Ridge, TN, Report No. ORNL-2422. [27] Messler , R. W. , 2004 , “ Brazing the Reactive Metals and Alloys ,” Joining of Materials and Structures: From Pragmatic Process to Enabling Technology , Elsevier Butterworth-Heinemann , Burlington, MA , pp. 554 – 556 . [28] Jones , H...

... was designed primarily to assess fission product transport through various graphite materials. Irradiation in the ATR started in December 2011 and finished in April 2014. Forty-eight (48) tristructural-isotropic-fueled compacts were inserted into 12 separate capsules for the experiment. The purpose...

... Technical White Paper , Crane Materials International, Atlanta, GA. http://www.isotecsecurity.com/isowp/wp-content/uploads/2016/03/aluminum_corrosion.pdf [4] Plankey , B. J. , Patterson , H. H. , and Cronan , C. S. , 1986 , “ Kinetics of Aluminum Fluoride Complexation in Acidic Water...