An accurate and portable solid state neutron rem meter

被引:14
|
作者
Oakes, T. M. [1 ]
Bellinger, S. L. [2 ]
Miller, W. H. [1 ,4 ]
Myers, E. R. [3 ]
Fronk, R. G. [2 ]
Cooper, B. W. [2 ]
Sobering, T. J. [5 ]
Scott, P. R. [3 ]
Ugorowski, P. [2 ]
McGregor, D. S. [2 ]
Shultis, J. K. [2 ]
Caruso, A. N. [3 ]
机构
[1] Univ Missouri, Nucl Sci & Engn Inst, Columbia, MO USA
[2] Kansas State Univ, Dept Mech & Nucl Engn, Manhattan, KS 66506 USA
[3] Univ Missouri, Dept Phys, Kansas City, MO 64110 USA
[4] Missouri Univ Res Reactor, Columbia, MO USA
[5] Kansas State Univ, Elect Design Lab, Manhattan, KS 66506 USA
关键词
Neutron dosimeter; Solid state neutron detector; Spectrometer; AMBIENT DOSE-EQUIVALENT; QUALITY FACTORS; SPECTROMETER; COUNTER; DESIGN; INSTRUMENT; DOSIMETER; DETECTOR; RANGE; MODERATOR;
D O I
10.1016/j.nima.2013.03.060
中图分类号
TH7 [仪器、仪表];
学科分类号
0804 ; 080401 ; 081102 ;
摘要
Accurately resolving the ambient neutron dose equivalent spanning the thermal to 15 MeV energy range with a single configuration and lightweight instrument is desirable. This paper presents the design of a portable, high intrinsic efficiency, and accurate neutron rem meter whose energy-dependent response is electronically adjusted to a chosen neutron dose equivalent standard. The instrument may be classified as a moderating type neutron spectrometer, based on an adaptation to the classical Bonner sphere and position sensitive long counter, which, simultaneously counts thermalized neutrons by high thermal efficiency solid state neutron detectors. The use of multiple detectors and moderator arranged along an axis of symmetry (e.g., long axis of a cylinder) with known neutron-slowing properties allows for the construction of a linear combination of responses that approximate the ambient neutron dose equivalent. Variations on the detector configuration are investigated via Monte Carlo N-Particle simulations to minimize the total instrument mass while maintaining acceptable response accuracy a dose error less than 15% for bare Cf-252, bare AmBe, an epi-thermal and mixed monoenergetic sources is found at less than 4.5 kg moderator mass in all studied cases. A comparison of the energy dependent dose equivalent response and resultant energy dependent dose equivalent error of the present dosimeter to commercially-available portable rem meters and the prior art are presented. Finally, the present design is assessed by comparison of the simulated output resulting from applications of several known neutron sources and dose rates. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:6 / 12
页数:7
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