Abstract: Provided is a fuel assembly for a boiling water reactor. The fuel assembly comprises fuel rod arranged in an 8-lines/8-columns square lattice, water rod and a channel box surrounding these fuel rods and water rods. A central portion corresponds to 80% of the fuel rod comprises fuel pellet having an outer diameter of 10.31 mm and inner diameter of 5.95 mm.

Abstract: The pressure P.sub.R in the reactor pressure vessel, the flow rate W.sub.c of the cooling water flowing through the core in the reactor pressure vessel, and the flow rate W.sub.STM of the steam supplied from the reactor pressure vessel to the turbine are detected. The enthalpy H.sub.f of the saturated cooling water is determined on the basis of the pressure P.sub.R. The values of the cooling water flow rate W.sub.c, the steam flow rate W.sub.STM, the enthalpy H.sub.f of the saturated cooling water and a predetermined enthalpy H.sub.IN of the cooling water at the core inlet are substituted into the equation below thereby to obtain the enthalpy H.sub.fw of the feed water. ##EQU1## An error is determined between the feed-water enthalpy H.sub.fw thus obtained and the enthalpy T.sub.

Abstract: A core construction for a nuclear reactor having a multiplicity of fuel cells forming a core in which each fuel cell includes four fuel assemblies arranged in adjacent relationship and one control rod insertable into a position surrounded by the four fuel assemblies. The fuel cells includes first fuel cells each having a relatively high cell mean infinite neutron multiplication factor and including one fuel assembly containing a burnable poison, and second fuel cells each having a relatively low cell mean infinite neutron multiplication factor and including no fuel assembly containing a burnable poison. The first fuel cells are arranged both in a central zone of the core disposed within about one-half the core radius from the center of the core and in a circumferential zone of the core outside the central zone. The second fuel cells are arranged only in the central zone and no second fuel cells are arranged in the circumferential zone.

Abstract: A method of operating a nuclear reactor adapted to use cross-shaped control rods. The control rods are grouped into a plurality of groups having a first group consisting of a control rod located at the center of the core, a second group consisting of 8 control rods surrounding the control rod of the first group, a third group consisting of control rods located adjacent to and outside of the control rods of the second group, and other groups determined successively in the same manner as in the third group. During the operation period other than the period in which the number of the control rods to be inserted for realizing the critical condition of said nuclear reactor is less than 6, the nuclear reactor is operated with control rod patterns in which the inserted control rods are selected from control rods of alternate or every other groups of said groups so as to include at least a pair of control rods which are located in a similar manner to that of the KNIGHT's movement on a chess board.

Abstract: There is provided a novel initial core arrangement of a nuclear reactor. The fuel assemblies in the central region of the reactor core occupying more than 50% of the total area of the reactor core are grouped into a plurality of fuel units each of which being constituted by four adjacent fuel assemblies. The fuel assemblies in each fuel unit are replaced one by one at each fuel replacement cycle with a new fuel assembly. The initial core is so arranged that each fuel unit has one gadolinia containing high enrichment fuel assembly and three low enrichment fuel assemblies containing no gadolinea. This arrangement permits a stable reactor operation substantially equivalent to that obtained in the state of equilibrium (equilibrium core), even with an initial core.

Abstract: A boiling water type nuclear reactor adapted to be operated at a void quality (weight ratio of vapor in the coolant) of coolant at the core outlet of 17% or higher. By adopting this level of void quality, a void quality exceeding 8.5% is available at least in the upper half region of the core which in turn provides a void fraction of 66% or higher. Consequently, it is possible to reduce the enrichment of the fuel, so as to allow a more efficient use of the fuel. At the same time, due to the reduced power generating rate, the range over which the flow rate of coolant is controlled is widened, so that it becomes possible to change the reactivity solely by controlling the flow rate of the coolant. It is therefore possible to operate the reactor over whole operation cycle with its control rods fully withdrawn.

Abstract: A method of operating a nuclear reactor wherein the reactor is operated for more than 50% of its operating period with the control rod patterns in which, in the central region of the reactor core accounting for at least 50% thereof, the control rods inserted from the bottom of the reactor core are at the depths of between 16/24 and 21/24 of the height of the reactor core with eight control rods surrounding each of said inserted control rods being fully withdrawn.

Abstract: A construction of boiling water reactor core having a plurality of fuel assemblies. Some of fuel assemblies have an infinite multiplication factor which is larger at their upper regions than at their lower portions, so that the effective multiplication factor of the reactor core is larger at the upper portion than at the lower portion of the reactor core under an equal condition. Consequently, a relatively flat axial power distribution is established even under an uneven axial void distribution.

Abstract: A fuel assembly suitable for use in boiling water reactor. The fuel assembly has a specific pattern of distribution of enrichment, so that the upper region of the assembly has a larger infinite multiplication factor than that of the lower region. In an example, the distribution of enrichment is such that the upper region has a mean enrichment larger than that of the lower region, while, in another example, the mean enrichment is maintained constant over the length of the assembly but the difference of enrichments between the central and peripheral portions of a plane normal to the axis of the assembly is made smaller at the upper region than at the lower region.