Abstract
Regarding the nuclear material accountancy and control for NUCEF: Nuclear Fuel Cycle Safety Engineering Research Facility, a computational program is developed in order to easily carry out analyses on calibration data of solution fuel accountancy vessels. The program supports executing the regression analysis on the data both of liquid volume and level in the vessel, and determining relationships of them which are called calibration functions. As a result of benchmark tests, it was proved that such quantities computed with the program as partial regression coefficients and their errors, standard deviation, multiple correlation, cumulative probability density of F- and t-distribution etc. well agreed with those by a statistical analysis program package which is widely used. In addition, this program would be useful for carrying out the above-mentioned analyses at the other facilities handling the nuclear material solution as well as at NUCEF. This paper describes summary of the program, computational methods employed in it, results of benchmark tests and operating procedures of the program. (author).
Yanagisawa, Hiroshi
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Yanagisawa, Hiroshi.
Vessel calibration date analysis program: VESCAL.
Japan: N. p.,
1994.
Web.
Yanagisawa, Hiroshi.
Vessel calibration date analysis program: VESCAL.
Japan.
Yanagisawa, Hiroshi.
1994.
"Vessel calibration date analysis program: VESCAL."
Japan.
@misc{etde_10102315,
title = {Vessel calibration date analysis program: VESCAL}
author = {Yanagisawa, Hiroshi}
abstractNote = {Regarding the nuclear material accountancy and control for NUCEF: Nuclear Fuel Cycle Safety Engineering Research Facility, a computational program is developed in order to easily carry out analyses on calibration data of solution fuel accountancy vessels. The program supports executing the regression analysis on the data both of liquid volume and level in the vessel, and determining relationships of them which are called calibration functions. As a result of benchmark tests, it was proved that such quantities computed with the program as partial regression coefficients and their errors, standard deviation, multiple correlation, cumulative probability density of F- and t-distribution etc. well agreed with those by a statistical analysis program package which is widely used. In addition, this program would be useful for carrying out the above-mentioned analyses at the other facilities handling the nuclear material solution as well as at NUCEF. This paper describes summary of the program, computational methods employed in it, results of benchmark tests and operating procedures of the program. (author).}
place = {Japan}
year = {1994}
month = {Aug}
}
title = {Vessel calibration date analysis program: VESCAL}
author = {Yanagisawa, Hiroshi}
abstractNote = {Regarding the nuclear material accountancy and control for NUCEF: Nuclear Fuel Cycle Safety Engineering Research Facility, a computational program is developed in order to easily carry out analyses on calibration data of solution fuel accountancy vessels. The program supports executing the regression analysis on the data both of liquid volume and level in the vessel, and determining relationships of them which are called calibration functions. As a result of benchmark tests, it was proved that such quantities computed with the program as partial regression coefficients and their errors, standard deviation, multiple correlation, cumulative probability density of F- and t-distribution etc. well agreed with those by a statistical analysis program package which is widely used. In addition, this program would be useful for carrying out the above-mentioned analyses at the other facilities handling the nuclear material solution as well as at NUCEF. This paper describes summary of the program, computational methods employed in it, results of benchmark tests and operating procedures of the program. (author).}
place = {Japan}
year = {1994}
month = {Aug}
}