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核动力堆安全壳内外中子能谱和剂量测量 被引量:11

Measurements of Neutron Spectra and Doses Inside and Outside the Containment of a Power Reactor
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摘要 利用自制的多球谱仪测量了某核动力反应堆安全壳内外的中子能谱和剂量当量率。对安全壳外测量 ,中心探测器为球形3 He正比计数管 ;对安全壳内测量 ,中心探测器为球形金箔。系统的响应函数用MCNP程序计算 ,解谱程序为MIEKEB。为验证系统响应函数计算的准确性 ,进行了一些实验测量 ,并与理论计算结果进行了比较。结果表明 ,测量结果与计算结果在不确定度范围内相吻合。 The neutron spectra and the neutron dose equivalent rates inside and outside the containment of a power reactor were measured with two multi-sphere spectrometer systems that the central detectors were a spherical gold foil and a spherical 3He proportional counter, respectively. The response functions were calculated by MCNP code, and MIEKEB code was used for unfolding. Some experiments were done in order to verify the accuracy of the calculated response functions of these systems. The measured results were compared with the calculated results. It is shown that they are accordant with in their uncertainties.
作者 陈军
出处 《原子能科学技术》 EI CAS CSCD 2004年第2期131-136,共6页 Atomic Energy Science and Technology
关键词 核动力堆 安全壳 中子能谱 剂量测量 多球谱仪 探测器 Calculations Computer software Containment vessels Nuclear reactors Radiation counters
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参考文献5

  • 1[1]Wiegel B, Alevra AV, Siebert BRL. Calculations of the Response Functions of Bonner Spheres With a Spherical 3He Proportional Counter Using a Realistic Detector Model:PTB-N-21[R]. Braunschweig, Germany:Physikalisch-Technische-Bundesanstalt, 1994.
  • 2[2]Matzke M. Unfolding of Pulse Height Spectra--The HEPRO Program System:PTB-N-19[R]. Braunschweig, Germany:Physikalisch-Technische-Bundesanstalt, 1994.
  • 3[3]ISO8529-3(1989), Neutron Reference Radiation-Part 3--Calibration of Area and Personal Dosimeters and Determination of Response as a Function of Energy and Angle of Incidence[S].
  • 4[4]ISO 1993(E), Guide to Expression of Uncertainty in Measurement[S].
  • 5[5]Matzke M. Propagation of Uncertainties in Unfolding Procedures:PTB-S7-01[R]. Braunschweig, Germany: Physikalisch-Technische-Bundesanstalt, 1994.

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