Heat accumulators at nuclear power stations

Conclusions It has been shown to be technically possible and economically desirable to introduce heat accumulators into nuclear power stations and CHPS, particularly FWA, DHWA, and DSWA. The largest power-control range is attained with HA of DHWA, PTA, and DSWA types and is 120–140% for stations with HA of the water class in relation to the nominal reactor power or up to 160% for stations with PTA.The inclusion of HA in a nuclear station provides higher PUF and consequently maintains high rates of production for secondary nuclear fuel with nuclear stations working in variableload mode. The introduction of HA at nuclear stations will enable one to fit turbines of power 1.2–1.4 times larger than the reactor power with HA of the water class or by more than a factor 1.5 for PTA, which provides a reliable means of covering peak loads by means of nuclear stations.Translated from Atomnaya Énergiya, Vol. 56, No. 6, pp. 389–396, June, 1984.     

The dynamics of nuclear power stations

This paper makes a comparison of the results of eXperimental and theoretical studies that have been carried out on the properties of the engineering model of the Beloyarskii atomic electric station under construction in the USSR, which uses nuclear superheating of the steam. It is shown that a number of the simplifying assumptions are correct which are often used in discussing the dynamics of nuclear power stations.The results of the studies may be used to make a theoretical analysis of the dynamic properties of several types of nuclear power installations, as well as in analyzing and synthesizing the optimum control system.Notation q() specific heat load, referred to length of segment, kcal/hour · m - f(x) distribution function of specific heat load along the length of segment - () heat transfer coefficient, including the thermal resistence of the fuel element, kcal/m² · hour · degree - t_f.e. (x, ) the current value of fuel element temperature, averaged over the corss section, degrees C - t(x, t) current value of coolant temperature, degrees C - p perimeter of fuel element, bathed by coolant, m - m weight of metal per unit length of fuel element kg/m - C_M heat capacity of metal and fuel element, kcal/kg · degree - i(x, ) current value of heat content of coolant, kcal/kg - specific gravity of coolant, kg/m³ - S live cross section of fuel element, m² - D(x, ) current value of flow of steam phase, kg/hour - G(x, ) current value of the flow of water phase, kg/hour - (x, ) current value of the fraction of the cross section occupied by steam - , specific gravity of water and steam at saturation temperature, kg/m² - i, i heat content of water and steam at saturation temperature, kcal/kg - t_S() saturation temperature, degrees C - P_i() pressure in i-th segment, kg/m² - l height, determining the level pressure between segments, m - g acceleration of gravity, m/hour² - w_i() coolant velocity at the i-th segment, m/hour - D_i() steam flow at the i-th segment of the superheating circuit, kg/hour - V_i volume of i-th segment of the superheating circuit, m³ - mean steam temperature at the i-th segment for the superheating circuit, degrees C - k₁,k₂,k₃,k₄ constant coefficients - N/N₀ relative power change in the evaporating channels, % - P_I, P_II pressure change in the first and second loops, atm - t_sps, t_fw change in temperature of superheated steam and feed water, respectively, degrees C Translated from Atomnaya Énergiya, Vol. 15, No. 2, pp. 115–120, August, 1963     

Qualification of equipment for nuclear power generating stations

The seismic qualification of equipment is demonstrated by test or analysis or combined test and analysis. Equipment generally have strong coupling of responses in different directions. In the qualification by analysis, the three components of the specified vibratory motions are considered. In the case of qualification by test, the qualification can be incomplete, as generally only two components of the vibratory motion are applied simultaneously. In the tests, concurrent thermal pressure, mechanical and vibratory loads are not applied simultaneously. As the flexibility of the floor can have a significant influence on the response to vibratory motions, such flexibilities should be considered in the development of the floor response spectra, used in the qualification of equipment.     

Desirability of composites for shielding nuclear power stations

All-Union Experimental Physics Research Institute. Translated from Atomnaya Énergiya, Vol. 75, No. 1, pp. 45–48, July, 1993.