共查询到20条相似文献,搜索用时 31 毫秒
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Yu. B. Kurdyaev 《Atomic Energy》2000,88(2):88-93
The problem of determining the parameters of the field of a cylindrical absorbing radiator in the direction of the generator
was solved for the case where the detection point lies outside the cylindrical surface of the radiator. A program of integrating
the expression obtained numerically was developed. The results of calculations of the position of the dose rate isolines were
presented for two radiators with relative heights 1 and 10. The maximum error was determined for the chosen numerical integration
parameters relative to the exact solution: this error was found to be no greater than 2% for the interval of relative heights
of the radiator 0.01–10. It was shown that the proposed scheme for obtaining the integral expression is much mor accurate
than the scheme used previously for calculation of the parameters of the field in a range falling within the height of the
radiator, 5 figures, 5 references.
Affiliate of the North-West Civil Service Academy. Translated from Atomnaya énergiya, Vol. 88, No. 2, pp. 88–92. 相似文献
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V. A. Tsykanov A. V. Klinov V. A. Starkov M. N. Svyatkin Z. I. Chechetkina E. F. Kartashev V. A. Lukichev A. V. Morozov V. S. Volkov 《Atomic Energy》2007,102(2):100-107
The first phase of the work on checking the main assumptions of the concept for upgrading the core of the SM reactor has been
completed. A full-scale reactor experiment has been performed for the purpose of creating in the reactor the conditions necessary
for accelerated high-dose irradiation of materials, meeting the requirements for the fast-neutron flux density, water temperature,
pressure, and composition, and making it possible to install large-diameter experimental channels and apparatus for regulating
the temperature and neutron spectrum. The decrease of the fuel volume and excess reactivity are compensated by a 20% increase
of the uranium content in a fuel element and by replacing the corrosion-resistant steel fuel-assembly jackets with zirconium-alloy
jackets. The results of the calculations and experiments performed during the first phase have shown that the objective has
been achieved-the reactor can be operated efficiently with the new arrangement of the core.
The objective and problems of the second phase are formulated: increase of the neutron flux density in the experimental channels
by a factor of 1.5 by increasing the power density in the core, using a fuel element with a low harmful absorption of neutrons,
and equalizing the power-release distribution by using a consumable absorber.
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Translated from Atomnaya énergiya, Vol. 102, No. 2, pp. 86–92, February, 2007. 相似文献
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Translated from Atomnaya Énergiya, Vol. 64, No. 5, pp. 349–353, May, 1988. 相似文献
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A. S. Kochenov 《Atomic Energy》1966,21(2):725-730
The influence of the parameters of a research reactor on the thermal-neutron flux in the reflector and the cost of the fuel required is considered. It is shown that, the higher the neutron breeding factor and the smaller the radius of the active zone, the greater is the ratio of the maximum thermal-neutron flux to the reactor power, This ratio is in particular quite large for reactors of the water-cooled, water-moderated type operating with intermediate neutrons. From the point of view of minimum fuel cost in experimental reactors, it is undesirable to choose either very low or very deep burnup.Translated from Atomnaya Énergiya, Vol. 21, No. 2, pp. 97–101, August, 1966. 相似文献