Research on the determination of 235U fission number by delayed γ-rays absorbed dose rates

SHANG Jianbo; SHI Quanlin; LIU Jie

doi:10.11889/j.0253-3219.2014.hjs.37.030201

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Research on the determination of 235U fission number by delayed γ-rays absorbed dose rates

更新时间：2021-03-03

- Research on the determination of 235U fission number by delayed γ-rays absorbed dose rates
- NUCLEAR TECHNIQUES Vol. 37, Issue 3, Article number: 030201(2014)
- 作者机构：
  
  1. 清华大学工程物理系,北京,100084
  2. 西北核技术研究所,西安,710024
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2014.hjs.37.030201
  CLC：
- Published：14 March 2014
- 稿件说明：
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SHANG Jianbo, SHI Quanlin, LIU Jie. Research on the determination of 235U fission number by delayed γ-rays absorbed dose rates[J]. Nuclear techniques, 2014, 37(3): 030201
DOI：

SHANG Jianbo, SHI Quanlin, LIU Jie. Research on the determination of 235U fission number by delayed γ-rays absorbed dose rates[J]. Nuclear techniques, 2014, 37(3): 030201 DOI： 10.11889/j.0253-3219.2014.hjs.37.030201.

摘要

裂变数的测定通常是利用HPGe探测器无损测量的方法，但这种方法难以在高辐射通量情况下获取实时数据。针对上述场景，本文引入了剂量率测定裂变数的方法，并进行了可行性验证。本文利用数值计算方法计算裂变产物衰变链上各核素含量随时间动态变化情况，结合CENDL3.0库及ENDF BVII.1库中的产额数据及核衰变数据，计算了热中子辐照铀靶后距裂变产物约1 m处空气总吸收剂量率随时间的变化规律。在西安脉冲反应堆跑兔装置上辐照铀靶，跟踪了距裂变产物约0.5 m处总吸收剂量率变化曲线，结合理论计算结果获取了裂变数。计算均值与后期高纯锗探测器测量铀靶所得裂变数偏差为7%，这表明利用缓发?射线剂量率测定235U裂变数的方法可行，可用于较强剂量场下快速确定核燃料的裂变数。

Abstract

Background: The determination method of 235U fission number by detecting fission products using HPGe detector has been established before. But in some special cases

we need to get the fission number in-time in high intensity radiation environment. HPGe detector has its limitation due to the complex g spectrum accompany with high flux. Purpose: To get rid of the limitation mentioned above

a new method is introduced by detecting the delayed g-rays absorbed dose rates. Methods: By using independent fission yield together with radioactive decay dates from CENDL 3.0 and ENDF BVII.1

dynamic calculation for total absorbed dose rate in air 1 meter from the source whose compositions were thermal neutron-induced fission products of 235U has been done. Results: A set of absorbed dose rate data of 235U fission products irradiated through fast rabbit irradiation system on Xi’an pulse reactor was recorded. The deviation of the fission neutron number between method by g-rays absorbed dose rates and method by HPGe detector is 7%. Conclusion: It’s feasible to determine the fission neutron number of 235U using delayed g-rays absorbed dose rates in a high intensity radiated environment.Cited

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