KNVK vacuum fission chambers for measuring neutron flux density

Malyshev, E. K.; Chuklyaev, S. V.; Shchetinin, O. I.

doi:10.1007/bf01123493

At Energy

1987

DOI: 10.1007/bf01123493

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KNVK vacuum fission chambers for measuring neutron flux density

E. K. Malyshev¹,

S. V. Chuklyaev²,

O. I. Shchetinin³

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Cited by 5 publications

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“…Vacuum Fission Chamber. The KNVK chamber, compensated with respect to the current from the external γ-radiation, contains a system of three electrodes placed in a hermetic case [2][3][4] (Fig. 1).…”

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confidence: 99%

Fission vacuum chambers and secondary-emission detectors as effective tools for measuring the characteristics of γ and neutron radiation from intense sources

Chuklyaev¹,

Dovbysh

Koshelev

2010

At Energy

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The results of measurements of the flux of fast neutrons in the density range 2·10 8 -2·10 19 sec -1 ·cm -2 and γ-ray dose rate in the range 2·10 -3 -1·10 9 Gy/sec in different operating regimes of pulsed nuclear reactors and accelerators are presented. The parameters of the delayed photon radiation are presented.Intense sources of neutrons are used for scientific research and testing materials and articles [1]. Efficient and informative checking of the characteristics of the radiation is accomplished in neutrons sources equipped with vacuum chambers and electronic apparatus.The present article gives the results of measurements of the fast-neutron flux density in the range 2·10 8 -2·10 19 sec -1 ·cm -2 and γ-ray dose rate in the range 2·10 -3 -1·10 9 Gy/sec in different operating regimes of nuclear reactors and a linear accelerator. The parameters of the delayed photon radiation are determined.Formation of the Radiation Field in a Reactor Pulse. The power of a reactor is determined by fission rate of nuclei in the core -dN f /dt. The fast-neutron flux arising in the process ϕ n is proportional to dN f /dt and the power of the reactor.The time dependence of the absorbed dose rate of photon radiation P γ can be represented in the form P γ (t) = P pr (t) + P del (t) + P nγ (t) + P ph ,where P pr and P del are the dose rates due to prompt and delayed photons, respectively; P nγ is the dose rate due to photon radiation emitted in the process of neutron moderation; P ph is the dose rate due to photon radiation in the stopped reactor. In an operating reactor, the total absorbed dose rate from prompt and delayed photons, arising in the process of moderation of the fast neutrons, is substantially higher that the photon dose rate in a stopped reactor. For this reason, we shall write relation (1) in the form P γ (t) = P pr (t) + P del (t) + P nγ (t).Since the dose rate of the photon radiation is due to a fission reaction coefficient, the relation assumes the form P γ (t) = K γ1 ϕ n + K γ2 ϕ n* g + B(r)ϕ n* ζ,

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mentioning

confidence: 99%

Fission vacuum chambers and secondary-emission detectors as effective tools for measuring the characteristics of γ and neutron radiation from intense sources

Chuklyaev¹,

Dovbysh

Koshelev

2010

At Energy

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Modulated-signal ionization chambers for monitoring nuclear reactors

Chuklyaev¹

1992

At Energy

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Experience gathered in the use of evacuated fission chambers in the IBR-2 reactor

Malyshev¹,

Melikhov²,

Pepelyshev³

et al. 1990

At Energy

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KNVK vacuum fission chambers for measuring neutron flux density

Cited by 5 publications

References 1 publication

Fission vacuum chambers and secondary-emission detectors as effective tools for measuring the characteristics of γ and neutron radiation from intense sources

Fission vacuum chambers and secondary-emission detectors as effective tools for measuring the characteristics of γ and neutron radiation from intense sources

Modulated-signal ionization chambers for monitoring nuclear reactors

Experience gathered in the use of evacuated fission chambers in the IBR-2 reactor

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