Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (7): 70201-070201.doi: 10.11889/j.0253-3219.2017.hjs.40.070201

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

Measurement of fission product yields on 238U induced by 14.8-MeV neutrons

SUN Qi, LUO Xiaobing, LI Wanqiong, WANG Chao, LI Ziyue   

  1. Key Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, China
  • Received:2017-02-06 Revised:2017-04-11 Online:2017-07-10 Published:2017-07-10
  • About author:10.11889/j.0253-3219.2017.hjs.40.070201
  • Supported by:
    Supported by Key Laboratory of Neutron Physics, China Academy of Engineering Physics (No.2014BA06)

Abstract: Background: The precise measurement of fission product yields is significant to many aspects of fission, because it's an important parameter in fission procedure. Purpose: The aim is to measure fission product yields of 238U induced by neutrons accurately. Methods: The T(d, n)4He reaction on the PD-300 accelerator of China Academy of Engineering Physics was used to produce 14.8-MeV neutrons. The neutron flux was monitored by Au(Si) surface barrier semiconductor detector during the irradiation. The average neutron flux in the whole process of irradiation was calculated by Al. After the irradiation, the sample was placed in front of a high purity germanium detector to measure the characteristic gamma rays of the fission products. Then cumulative yields were calculated through the counts. The Monte Carlo program MCNPX was used to estimate the effects of multiple scattering and self-shielding of neutrons. The corrections of self-absorption and the neutron flux fluctuation were also calculated. Results: The fission product yields for some long half-life radionuclide, i.e., 95Zr, 127Sb, 140Ba, 147Nd, 131I, 103Ru were determined. Conclusion: The results were compared with previous literature values, and they are helpful to the analysis and evaluation of 238U yield.

Key words: 238U, Fission yields, DT accelerator neutron source, Activation method, Monte Carlo

CLC Number: 

  • TL99