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Buckling of Thin Plates under Uniaxial and Biaxial Compression

材料科学与工程（中英文B版） 2012年第8期2卷 487-492页

作者： Mokhtar Bouazza Djamel Ouinas abdelaziz Yazid Abdelmadjid Hamouine Department of Civil Engineering University of Bechar Bechar 08000 Algeria Laboratory of Materials and Hydrology (LMH) University of Sidi Bel Abbes Sidi Bel Abbes 2200 Algeria Department of Mechanical Engineering University of Mostaganem 27000 Algeria

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Comparative Moisture Performance of Wood/Wood-Based Claddings Predicted by Four Hygrothermal simulation Tools

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Journal of Civil Engineering and Architecture 2021年第2期15卷 63-77页

作者： Maurice Defo Michael Lacasse abdelaziz Laouadi Mehdi Ghobadi National Research Council of Canada(NRC) 1200 Montreal RoadOttawa(ON)K1A 0R6Canada

A number of hygrothermal(HAM)numerical simulation packages are available,either wholly or partially dedicated to heat,air and moisture transfer simulations of building materials and wall *** objective of this work was to compare the HAM responses and moisture performance of western red cedar and composite wood claddings of a wood frame wall as predicted by four HAM simulation tools:DELPHIN,WUFI,hygIRC,and *** Canadian cities having different climates were selected for simulation:Ottawa(ON),Vancouver(BC)and Calgary(AB).In each city,simulations were run for two years as selected from a historical climate data set based on the moisture index(MI).The wall orientation receiving the most wind-driven rain for the two years was selected for *** properties were taken from the National Research Council(NRC)material property *** temperature and relative humidity(RH)values as well as the moisture accumulated in the entire structure were compared amongst the results obtained from the four *** mold growth index on the cladding surface was used as a basis for comparing the moisture performance.

关键词： HAM simulation tools HAM response mold index western red cedar cladding composite wood cladding

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Prediction of the Average Decay Heat per Fission for MOX Nuclear Fuel

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Journal of Applied Mathematics and Physics 2022年第3期10卷 887-899页

作者： Amir M. Alramady Hanan M. Barashed sherif s. Nafee Deanship of Post Graduate studies King Abdelaziz University Jeddah Kingdom of Saudi Arabia Department of Physics Faculty of Science King Abdulaziz University Jeddah Kingdom of Saudi Arabia Department of Physics Faculty of Science Hadhramout University Mukalla Yemen Department of Physics Faculty of Science Alexandria University Alexandria Egypt

MIXED Oxide Nuclear fuel (MOX) contains both uranium and plutonium in oxidized form. It is important to calculate the nuclear decay heat due to the single thermal fission (fission due to 0.0235 eV neutron) for all fissile nuclei in the MOX fuels (Usup>235sup>, Pusup>239sup>, and Pusup>241sup>). These fissile nuclei are the main source of the decay heat in MOX fuel. Decay heat calculation of the weighted fissile material content in MOX fuel is also important. A numerical method was used in this work to calculate the concentrations of all fission products due to the individual thermal fission of the three fissile materials as a function of time N(t). The decay heat calculations for the three fissile materials are directly calculated using the summation method by knowing the different concentrations of fission products over time. The average decay heat of the MOX fuel in induced thermal fission is also concluded. The most influential nuclei in the decay heat were also identified. The method used has been validated by several comparisons before, but the new in this work is using the most recent Evaluated Nuclear Data Library ENDF/B-VIII.0. Calculations of decay heat show very common trends for a period of 10sup>7sup> sec after the fission burst of thermal fissions of individual fissile nuclei. Moreover, the code showed high capability in calculating the fission fragments inventories and decay heats due to the decay of fission fragments of 31 fissionable nuclei.

关键词： Nuclear Decay Heat Fission Burst Fission Fragments MOX Fuel MATLAB

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