VELOCITY OF SOUND IN WATER CONTAINING GAS BUBBLES

The velocity of sounmd in water containing bubbles of hydrogen gas is computed as a function of the volume fraction of gas for various bubble sizes. Results indicate that the marked reduction in sound velocity caused by the presence of gas voids is not as great if the gas is present as very small bubbles. The results are used in qualitative observations concerning inertial pressures in fast excursions in the KEWB reactor. The qualitative conclusions are listed. (J.R.D.

On the Influence of Stochastic Moments in the Solution of the Neutron Point Kinetics Equation

On the Influence of Stochastic Moments in the Solution of the Neutron Point Kinetics EquationComment: 12 pages, 2 figure

The Response of a Water Boiler Reactor to Very Fast Power Transients and Linearly Increasing Reactivity Inputs. Water Boiler Excursions With an Initially Filled Core

A report is made on the Kinetic Experiment on Water Beller Program. The purpose of this program is to examine the dynamic behavior of homogeneous research reactors to obtain the information necessary for the evaluation of the nuclear safety of such reactors. Step inputs of reactivity were systematically increased and the first test core, a spherical core designed for stable power operation at 50 kw, was examined under conditions of 4% reactivity release This is the maximum normally installed in such reactors A 4% reactivity release places the reactor on a 2 millisecond stable period and leads to a peak power of 530 Mw. This represents the fastest intentional power excursion of any thermal reactor. The reactivity released is more than twice that which any other has withstood without damage. The maximum pressure in the system for this transient was a sharp pressure peak of 370 psia. This pressure is well below that required to cause yield of a typical water boller core. (A.C.

Thermohydraulic modeling and simulation of breeder reactors

This paper deals with the modeling and simulation of system-wide transients in LMFBRs. Unprotected events (i.e., the presumption of failure of the plant protection system) leading to core-melt are not considered in this paper. The existing computational capabilities in the area of protected transients in the US are noted. Various physical and numerical approximations that are made in these codes are discussed. Finally, the future direction in the area of model verification and improvements is discussed