Nuclear power plants with water-moderated water-cooled reactors in power systems: Adaptation methods

Saratov Polytechnic Institute. Translated from Atomnaya Énergiya, Vol. 71, No. 6, pp. 551–555, December, 1991.     

Determination of the neutron flux density outside the vessel of water-moderated/water-cooled power reactors of operating atomic electric power plants

Translated from Atomnaya Énergiya, Vol. 64, No. 2, pp. 155–156, February, 1988.     

Calculation of water-moderated water-cooled reactors

An expression is obtained for the probability of avoiding leakage in reactors with uniform energy evolution. From an analysis of this probability, together with the Fourier components of the experimental slowing-down function and the slowing-down functions of various diffusion models for ordinary water, it is concluded that the single group model is fairly accurate forthe calculation of active zones conraining not less than 10 liters of water. Increasing the number of energy groups without going over to nondiffusion theory lowers the precision.Translated from Atomnaya Énergiya, Vol. 17, No. 5, pp. 375–379. November, 1964     

Graphite-moderated,gas-cooled,and water-moderated,water-cooled reactors as power units in nuclearelectric power stations

The present article reviews a number of papers submitted at the Second International Conference on the Peaceful Uses of Atomic Energy bearing on water-cooled, water-moderated, graphite-moderated, and gas-cooled reactors abroad.The basic characteristics of all of the operational power reactors, as well as of the high-power, graphite-gas water-cooled, and water-moderated reactors built abroad are cited in the article.Differences in the pathways and means of development of nuclear power in different countries are given due acknowledgement. In Britain, for example, after the first generation reactors (Calder Hall type) were built, advanced second generation reactors (Hinkley Point, etc.) were introduced, and intensive studies are now underway on third generation reactors. The ultimate purpose of the research in progress is the development of a high- temperature reactor operating in a unit with the associated gas turbine. A transition in the USA from the classical pressurized-water reactor concept (PWR) to that of the boiling water reactor with direct steam feed to the turbine is planned.The continuous improvement in the efficiency of graphite-moderated, gas-cooled reactors and water-cooled, water-moderated reactors and the reduction in capital costs per unit rated power and in cost of power developed is shown.     

The optimum temperature for regenerative water-heating systems at atomic power stations with water-cooled and water-moderated power reactors (WWPR)

The base point method is used to determine the optimum temperature t _r ^opt for a regenerative water-heating system which corresponds to a minimum calculated cost c_e (kopeks/kwh) for electrical energy. It is shown that for an atomic power station having a water-cooled and water-moderated power reactor (WWPR) the value of t_r ^opt is near the maximum defined by the steam conditions after the first turbine stage.