14 shallow snow / firn cores were taken by drilling with the PICO lightweight hand coring auger on Law Dome and Wilkes Land along a line approximately 111 °E longitude between 66°S and 74°S latitude. 5 ...14 shallow snow / firn cores were taken by drilling with the PICO lightweight hand coring auger on Law Dome and Wilkes Land along a line approximately 111 °E longitude between 66°S and 74°S latitude. 5 of these cores, BJ, LJ24, GC30, GC40 and GC46, 20-30 m deep, are studied in detail in this paper. The densities of snow / firn were measured in a cold room at temperature between -18℃ and-14℃ by taking consecutive core samples and weighing the mass of each sample whose volume was known. The characteristics of the initial densification (till a density of 550 kg / m3) including the variation of snow / firn density with increasing depth, densification rate of snow / firn and the com-pactive viscosity coefficient of snow / firn are studied, and the factors affecting this initial densification process are discussed. From the obtained measurements, a relationship between compactive viscosity coefficient of snow / firn and mean annual temperature is found in case ρ=550 kg / m3 . For snow / firm on Wilkes Land, the relationship we found at a mean annual temperature below -25ccccccccccccccccc (i.e. no melting features are present in stratigraphy) is very similar to that found by Nishimura and others (1983) on Mizuho Plateau, Antarctica.展开更多
The phenomenology involved in severe accidents in nuclear reactors is highly complex.Currently,integrated analysis programs used for severe accident analysis heavily rely on custom empirical parameters,which introduce...The phenomenology involved in severe accidents in nuclear reactors is highly complex.Currently,integrated analysis programs used for severe accident analysis heavily rely on custom empirical parameters,which introduce considerable uncertainty.Therefore,in recent years,the field of severe accidents has shifted its focus toward applying uncertainty analysis methods to quantify uncertainty in safety assessment programs,known as“best estimate plus uncertainty(BEPU).”This approach aids in enhancing our comprehension of these programs and their further development and improvement.This study concentrates on a third-generation pressurized water reactor equipped with advanced active and passive mitigation strategies.Through an Integrated Severe Accident Analysis Program(ISAA),numerical modeling and uncertainty analysis were conducted on severe accidents resulting from large break loss of coolant accidents.Seventeen uncertainty parameters of the ISAA program were meticulously screened.Using Wilks'formula,the developed uncertainty program code,SAUP,was employed to carry out Latin hypercube sampling,while ISAA was employed to execute batch calculations.Statistical analysis was then conducted on two figures of merit,namely hydrogen generation and the release of fission products within the pressure vessel.Uncertainty calculations revealed that hydrogen production and the fraction of fission product released exhibited a normal distribution,ranging from 182.784 to 330.664 kg and from 15.6 to 84.3%,respectively.The ratio of hydrogen production to reactor thermal power fell within the range of 0.0578–0.105.A sensitivity analysis was performed for uncertain input parameters,revealing significant correlations between the failure temperature of the cladding oxide layer,maximum melt flow rate,size of the particulate debris,and porosity of the debris with both hydrogen generation and the release of fission products.展开更多
文摘14 shallow snow / firn cores were taken by drilling with the PICO lightweight hand coring auger on Law Dome and Wilkes Land along a line approximately 111 °E longitude between 66°S and 74°S latitude. 5 of these cores, BJ, LJ24, GC30, GC40 and GC46, 20-30 m deep, are studied in detail in this paper. The densities of snow / firn were measured in a cold room at temperature between -18℃ and-14℃ by taking consecutive core samples and weighing the mass of each sample whose volume was known. The characteristics of the initial densification (till a density of 550 kg / m3) including the variation of snow / firn density with increasing depth, densification rate of snow / firn and the com-pactive viscosity coefficient of snow / firn are studied, and the factors affecting this initial densification process are discussed. From the obtained measurements, a relationship between compactive viscosity coefficient of snow / firn and mean annual temperature is found in case ρ=550 kg / m3 . For snow / firm on Wilkes Land, the relationship we found at a mean annual temperature below -25ccccccccccccccccc (i.e. no melting features are present in stratigraphy) is very similar to that found by Nishimura and others (1983) on Mizuho Plateau, Antarctica.
基金This work was supported financially by the National Natural Science Foundation of China(No.12375176).
文摘The phenomenology involved in severe accidents in nuclear reactors is highly complex.Currently,integrated analysis programs used for severe accident analysis heavily rely on custom empirical parameters,which introduce considerable uncertainty.Therefore,in recent years,the field of severe accidents has shifted its focus toward applying uncertainty analysis methods to quantify uncertainty in safety assessment programs,known as“best estimate plus uncertainty(BEPU).”This approach aids in enhancing our comprehension of these programs and their further development and improvement.This study concentrates on a third-generation pressurized water reactor equipped with advanced active and passive mitigation strategies.Through an Integrated Severe Accident Analysis Program(ISAA),numerical modeling and uncertainty analysis were conducted on severe accidents resulting from large break loss of coolant accidents.Seventeen uncertainty parameters of the ISAA program were meticulously screened.Using Wilks'formula,the developed uncertainty program code,SAUP,was employed to carry out Latin hypercube sampling,while ISAA was employed to execute batch calculations.Statistical analysis was then conducted on two figures of merit,namely hydrogen generation and the release of fission products within the pressure vessel.Uncertainty calculations revealed that hydrogen production and the fraction of fission product released exhibited a normal distribution,ranging from 182.784 to 330.664 kg and from 15.6 to 84.3%,respectively.The ratio of hydrogen production to reactor thermal power fell within the range of 0.0578–0.105.A sensitivity analysis was performed for uncertain input parameters,revealing significant correlations between the failure temperature of the cladding oxide layer,maximum melt flow rate,size of the particulate debris,and porosity of the debris with both hydrogen generation and the release of fission products.
