Measurement of fission product yields on <sup>238</sup>U induced by 14.8-MeV neutrons

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

doi:10.11889/j.0253-3219.2017.hjs.40.070201

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

LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS | 更新时间：2021-05-19

- Measurement of fission product yields on ²³⁸U induced by 14.8-MeV neutrons
- NUCLEAR TECHNIQUES Vol. 40, Issue 7, Article number: 070201(2017)
- 作者机构：
  
  四川大学原子核科学技术研究所辐射物理及技术教育部重点实验室成都 610064
- 作者简介：
- 基金信息：
  
  Key Laboratory of Neutron Physics, China Academy of Engineering Physics
- DOI：10.11889/j.0253-3219.2017.hjs.40.070201
  CLC： TL99
- Received：06 February 2017，
  
  Revised：11 April 2017，
  
  Published：10 July 2017
- 稿件说明：
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Qi SUN, Xiaobing LUO, Wanqiong LI, et al. Measurement of fission product yields on ²³⁸U induced by 14.8-MeV neutrons[J]. Nuclear techniques, 2017, 40(7): 070201
DOI：

Qi SUN, Xiaobing LUO, Wanqiong LI, et al. Measurement of fission product yields on ²³⁸U induced by 14.8-MeV neutrons[J]. Nuclear techniques, 2017, 40(7): 070201 DOI： 10.11889/j.0253-3219.2017.hjs.40.070201.

摘要

裂变产物产额作为裂变过程的一个重要参数，其准确测量对有关裂变的很多方面都有重要意义。为了准确测量中子诱发

238

U裂变产物产额，利用中国工程物理研究院PD-300加速器上的T（d，n）

He反应，产生14.8MeV的中子，诱发

238

U裂变。辐照过程中，通过金硅面垒半导体探测器监测中子通量的变化。使用Al片作为监测片计算整个照射过程中样品的平均中子通量。辐照结束后，利用高纯锗（High-Purity Germanium

HPGe）探测器测得裂变产物特征γ射线计数，计算得到裂变产物的产额，使用MCNPX软件对中子的多次散射和自屏蔽效应进行修正，并通过计算得到样品和监测片的自吸收修正、中子通量波动因子。得到了

Zr、

127

Sb、

140

Ba、

147

Nd、

131

I、

103

Ru等长半衰期产物的累积产额值，并将结果与以前的文献值做了比对，研究结果有助于

238

U裂变产物产额的分析和评价。

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

238

U induced by neutrons accurately.

Methods

The T(d

He 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.

127

140

147

131

103

Ru were determined.

Conclusion

The results were compared with previous literature values

and they are helpful to the analysis and evaluation of

238

U yield.

关键词

Keywords

references

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

DOI：10.11889/j.0253-3219.2017.hjs.40.070201

摘要

Abstract

关键词

Keywords

references

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