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1.
Health Phys ; 123(1): 1-10, 2022 07 01.
Artigo em Inglês | MEDLINE | ID: mdl-35584312

RESUMO

ABSTRACT: The drift in response of neutron survey meters that employ moderated 3He and BF3 proportional counters has been reported and investigated by instrument calibration laboratories for over 20 y. When within a constant radiation rate field of high intensity, dose rate readings of an instrument may steadily increase with a rate proportional to the field intensity before reaching a relatively stable plateau. This phenomenon, commonly referred to as the radiation soaking effect, has been attributed to the accumulation of charge on insulating surfaces inside the detector. This paper provides results of a study specifically conducted to better understand the effect and, hence, to possibly identify mitigation techniques. The magnitude of the effect in different instruments tested under the same conditions has been assessed, and a reason for the detector response variance has been clearly identified. In addition to measures used in calibration practice to compensate for the radiation soaking effect, a potential method to return an instrument sensitivity to its baseline level is also discussed.


Assuntos
Nêutrons , Radiometria , Calibragem , Desenho de Equipamento , Doses de Radiação
2.
Health Phys ; 113(3): 183-194, 2017 09.
Artigo em Inglês | MEDLINE | ID: mdl-28749809

RESUMO

Evaluations of neutron survey instruments, area monitors, and personal dosimeters rely on reference neutron radiations, which have evolved from the heavy reliance on (α,n) sources to a shared reliance on (α,n) and the spontaneous fission neutrons of californium-252 (Cf). Capable of producing high dose equivalent rates from an almost point source geometry, the characteristics of Cf are generally more favorable when compared to the use of (α,n) and (γ,n) sources or reactor-produced reference neutron radiations. Californium-252 is typically used in two standardized configurations: unmoderated, to yield a fission energy spectrum; or with the capsule placed within a heavy-water moderating sphere to produce a softened spectrum that is generally considered more appropriate for evaluating devices used in nuclear power plant work environments. The U.S. Department of Energy Cf Loan/Lease Program, a longtime origin of affordable Cf sources for research, testing and calibration, was terminated in 2009. Since then, high-activity sources have become increasingly cost-prohibitive for laboratories that formerly benefited from that program. Neutron generators, based on the D-T and D-D fusion reactions, have become economically competitive with Cf and are recognized internationally as important calibration and test standards. Researchers from the National Institute of Standards and Technology and the Pacific Northwest National Laboratory are jointly considering the practicality and technical challenges of implementing neutron generators as calibration standards in the U.S. This article reviews the characteristics of isotope-based neutron sources, possible isotope alternatives to Cf, and the rationale behind the increasing favor of electronically generated neutron options. The evaluation of a D-T system at PNNL has revealed characteristics that must be considered in adapting generators to the task of calibration and testing where accurate determination of a dosimetric quantity is necessary. Finally, concepts are presented for modifying the generated neutron spectra to achieve particular targeted spectra, simulating Cf or workplace environments.


Assuntos
Califórnio/química , Nêutrons , Radiometria/instrumentação , Calibragem , Aceleradores de Partículas , Estados Unidos
3.
Health Phys ; 112(4): 364-375, 2017 04.
Artigo em Inglês | MEDLINE | ID: mdl-28234696

RESUMO

Radiation survey meters and personal dosimeters are typically calibrated in reference neutron fields based on conventional radionuclide sources, such as americium-beryllium (Am-Be) or californium-252 (Cf), either unmodified or heavy-water moderated. However, these calibration neutron fields differ significantly from the workplace fields in which most of these survey meters and dosimeters are being used. Although some detectors are designed to yield an approximately dose-equivalent response over a particular neutron energy range, the response of other detectors is highly dependent upon neutron energy. This, in turn, can result in significant over- or underestimation of the intensity of neutron radiation and/or personal dose equivalent determined in the work environment. The use of simulated workplace neutron calibration fields that more closely match those present at the workplace could improve the accuracy of worker, and workplace, neutron dose assessment. This work provides an overview of the neutron fields found around nuclear power reactors and interim spent fuel storage installations based on available data. The feasibility of producing workplace-like calibration fields in an existing calibration facility has been investigated via Monte Carlo simulations. Several moderating assembly configurations, paired with a neutron generator using the deuterium tritium (D-T) fusion reaction, were explored.


Assuntos
Calibragem/normas , Deutério/normas , Exposição Ocupacional/análise , Exposição à Radiação/análise , Monitoramento de Radiação/normas , Trítio/normas , Deutério/análise , Nêutrons , Exposição Ocupacional/normas , Exposição à Radiação/normas , Monitoramento de Radiação/instrumentação , Geradores de Radionuclídeos/instrumentação , Geradores de Radionuclídeos/normas , Reprodutibilidade dos Testes , Sensibilidade e Especificidade , Trítio/análise , Washington
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