Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (8): 80201-080201.doi: 10.11889/j.0253-3219.2016.hjs.39.080201

• LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS • Previous Articles     Next Articles

Nondestructive determination of the 238U content in mental uranium sample by using the activation method

WANG Chao1, XIAO Jun2, WANG Pan1, LI Yingying1, LI Ziyue1, LUO Xiaobing1   

  1. 1 Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, China;
    2 Key Laboratory for Neutron Physics, China Academy of Engineering Physics, Mianyang 621900, China
  • Received:2016-01-22 Revised:2016-04-01 Online:2016-08-10 Published:2016-08-15
  • Supported by:

    Supported by Key Laboratory of Neutron Physics, China Academy of Engineering Physics (No.2014BA06)

Abstract:

Background: As a kind of important fission material, the accurate quantification of 238U is of great significance in the measurement of fission yield data. Purpose: The aim is to nondestructively measure the content of 238U by using the activation method. Methods: Neutron of 483-keV produced by the reaction of T(p,n)3He induces 238U occurring radiative capture reaction on the 2.5-MeV electrostatic accelerator of Sichuan University. The atomic number of 238U in uranium samples is measured by using 278-keV gamma ray of 239Np on the detector of high purity germanium (HPGe) and the data of capture cross section. Results: The deflections which were caused by multiple scattering and self-shielding of the target and sample in the experiment were corrected with MCNPX (Monte Carlo N-Particle eXtended). The result of the experiment is that the atomic number of 238U in the 2.884 2-g metal uranium is 5.712 8×1021. Conclusion: The uncertainty of the experimental result is 4.1%. We can reduce the effect of multiple scattering effects and self-shielding by decreasing the thickness of the bottom lining, target tube, water layer and cladding material of the sample.

Key words: Quantification analysis of 238U, Data of capture cross section, Monte Carlo correction

CLC Number: 

  • TL99