Calculation of the parameters of the field of a cylindrical absorbing radiator in the direction of the generator

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.     

Cryoirradiation in the nuclear IRT reactor of the Institute of Physics of the Academy of Sciences of the Georgian SSR

Translated from Atomnaya Énergiya, Vol. 64, No. 5, pp. 349–353, May, 1988.     

Main results of the first phase of the upgrade of the SM core

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. __________ Translated from Atomnaya énergiya, Vol. 102, No. 2, pp. 86–92, February, 2007.     

Effect of the parameters of a research reactor on the flux of thermal neutrons in the reflector and the cost of the fuel

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.     

对因工作人员走错机组隔间导致的核电厂人因事件的探讨

介绍了一起因走错机组隔间导致误操作继而引发反应堆停堆的运行事件。通过对这一类型事件的深入探讨,找出导致事件发生的原因,提出了改进建议。可为其他核电厂提供参考,以期避免类似事件的重复发生。