1994He huaxue yu fangshe huaxueRequires access

MULTINUCLIDE METHOD FOR DETERMINATION OF FISSION QUANTITY OF MIXED FISSILE MATERIAL

Ding Youqian

Open publisher page 0 citations

Abstract

A new methd──multinuclide method is proposed for the determination of fission quanti-ties of mixed fissile material.Both total fission quantity and partial fission quantities of individualfissile materials can be obtained simultaneously by determining the number of nucleus of some fis-sion products with linear least-square method,in which the virtual fission quantity is y axis andthe ratio of fission yields for fissile materials is x axis,i.e.n_i is virtual fission quantity;y ̄A_i is yield of fission product i for fissile material A;Y ̄B_i is yield of fis-sion product i for fissile material B;n ̄A_f is fission quantity of A;n ̄B_f is fission quantity of B;A and Bare fissile materials,The intercept at yaxis is fission quantity of A and the n_i vaule at Y ̄B_i/Y ̄A_i=1 istotal fission quantity.The key of using this method is how to select fission products and theiryields,The rule of selection of fission preducts is discussed.

About this research paper

What this paper is about

A new methd──multinuclide method is proposed for the determination of fission quanti-ties of mixed fissile material.Both total fission quantity and partial fission quantities of individualfissile materials can be obtained simultaneously by determining the number of nucleus of some fis-sion products with linear least-square method,in which the virtual fission quantity is y axis andthe ratio of fission yields for fissile materials is x axis,i.e.n_i is virtual fission quantity;y ̄A_i is yield of fission product i for fissile material A;Y ̄B_i is yield of fis-sion product i for fissile material B;n ̄A_f is fission quantity of A;n ̄B_f is fission quantity of B;A and Bare fissile materials,The intercept at yaxis is fission quantity of A and the n_i vaule at Y ̄B_i/Y ̄A_i=1 istotal fission quantity.The key of using this method is how to select fission products and theiryields,The rule of selection of fission preducts is discussed.

Why it matters

A significance statement is not available in the OpenAlex record.

Key contribution

A contribution statement is not available in the OpenAlex record.

Method / approach

Method details are not available in the OpenAlex metadata.

Main findings

Findings are not separately available in the OpenAlex metadata.

Limitations

Limitations are not available in the OpenAlex metadata.

Applications

Application details are not available in the OpenAlex metadata.

Available abstract

A new methd──multinuclide method is proposed for the determination of fission quanti-ties of mixed fissile material.Both total fission quantity and partial fission quantities of individualfissile materials can be obtained simultaneously by determining the number of nucleus of some fis-sion products with linear least-square method,in which the virtual fission quantity is y axis andthe ratio of fission yields for fissile materials is x axis,i.e.n_i is virtual fission quantity;y ̄A_i is yield of fission product i for fissile material A;Y ̄B_i is yield of fis-sion product i for fissile material B;n ̄A_f is fission quantity of A;n ̄B_f is fission quantity of B;A and Bare fissile materials,The intercept at yaxis is fission quantity of A and the n_i vaule at Y ̄B_i/Y ̄A_i=1 istotal fission quantity.The key of using this method is how to select fission products and theiryields,The rule of selection of fission preducts is discussed.

Key concepts: Fissile material, Fission, Fission product yield, Fission products, Long-lived fission product, Nuclear fission product, Chemistry, Fast fission

Related papers

Back to paper searchBrowse research topicsOriginal source
MULTINUCLIDE METHOD FOR DETERMINATION OF FISSION QUANTITY OF MIXED FISSILE MATERIAL — Research Paper | ScholarLens