Patent Number: 041697596
Section: description

DESCRIPTION OF THE PREFERRED EMBODIMENT The part length rod design described herein is illustrated in the FIGURE. The nuclear reactor 10 generally includes nuclear reactor core 12 with length L, pressure vessel 14, control rod drive mechanisms 16 attached to nozzles 18 which penetrate the reactor pressure vessel 14 and part length rods 22 and 22' of length L connected to the control rod drive mechanisms 16 by means of connecting elements 20. The part length control rods 22, 22' of the invention have two neutron absorbing regions 24 and 26. Normal, full length control rods (an example of which shown at 23) constitute a first group of rods insertable into the core for normal control of reactor power, and the part length rods 22, 22' constitute a second group of control rods for control of power oscillations. Part length control rod 22 is shown in its normal control position approximately centrally positioned in the reactor core. Part length control rod 22' is shown in its scrammed or fully inserted position in which both poison sections 24 and 26 are positioned within the reactor core 12 at opposite ends of the core 12. Each part length control rod 22, 22' is translatable from a full out position to a full in position. As can be seen in the FIGURE, poison portions 24 and 26 are connected by an intermediate connecting portion 28. This intermediate connecting portion 28 acts as a poison section "follower". In the preferred embodiment the "follower" section 28 is a water filled Inconel tube designed to achieve the minimum reactivity control worth obtainable. Hence, by use of a water filled follower, the maximum effective control worth of the lower control portion 26 is obtained. On either part length control rod 22, 22' the first portion 24 appears at a first end of the part length rod 22, 22' and consists of a first neutron absorbing material. A second portion 26 appears at the second end of the part length rod 22, 22' and consists of a second neutron absorbing material. The second neutron absorbing material 26 preferably has a smaller macroscopic absorption cross-section than the first neutron absorbing material 24. For the purposes of this disclosure the terminology "macroscopic absorption cross-section" is defined to be the product of the number density of the particular element in question and the microscopic neutron absorption cross-section of the element in question. Accordingly, it is a desirable feature of the invention to provide the second portion 26 of the part length control rod 22, 22' with a macroscopic absorption cross-section that is smaller than the macroscopic absorption cross-section of the first portion 24 by providing a material with a high number density but with a low microscopic neutron absorption cross-section. This combination is desirable since it resists depletion of the neutron poison more readily than would a neutron poison resulting from the combination of a smaller number density but a larger microscopic neutron absorption cross-section. A well-known material in the science of nuclear reactor design which meets these requirements is the alloy Inconel 600. Inconel 600 is defined by the Standard Handbook For Mechanical Engineers by Baumeister and Marks, 7th Edition as having the following composition: (76Ni 0.04C--0.2MN--7.20Fe--0.2Si--0.1Cu--15.8Cr). An alternative and equally as acceptable material is Inconel 625 (61Ni--21Cr--9Mo). In the preferred embodiment of this disclosure the second neutron absorbing material located at the second end of the part length rod is preferably between 25 and 55 percent of the length of the active region of the nuclear core. Such a part length rod made from Inconel 600 has a longer and a weaker nuetron absorbing section than has previously been known in the prior art. This longer and weaker neutron absorbing section has many advantages. One positive advantage is that the longer weaker neutron absorbing section reduces the possibility of incurring nuclear fuel failure. Although the mechanism for nuclear fuel pin clad failure through fuel interaction has not been completely established, it is generally agreed that the magnitude and rate of change of local power density in a fuel pellet are important components of the failure mechanism. Since fuel pellets in the vicinity of control rods experience severe changes in local power density as the tip of the poison section moves past them, those pins are prime candiates for interaction induced clad failure. In modern larger nuclear cores the instabilities with respect to axial xenon oscillations are expected very early in the fuel life cycle. Although this presents no operational difficulties, it does require the presence, and continued motion of, the part length rods which have been provided to control axial power distribution. This control is accomplished by positioning the longer weaker portion of the part length control rod substantially in the center of the reactor core. When a neutron flux imbalance arises at either end of the core, the part length control rod is moved in the direction of higher neutron flux to reduce the neutron flux imbalance. Interaction as a result of part length rod motion is of concern under two separate conditions of operation. The first of these is motion of the part length rod out of a region in which they were formerly inserted, such as would occur during load follow maneuvering control or removal of the part length rod from the core. The second is the smaller motion of the part length rod required to control neutron flux imbalance or axial xenon oscillations. One benefit expected to be derived from the part length rod of the present invention is that the increase in the local power density as the part length rod is removed from the center of the core, is significantly less for the part length rod of the present invention as compared to the prior art part length rods. Removal of a previous prior art boron carbide part length rod bank is characterized by an increase in power of over 200 percent relative to the original power at the center of the rod. Removal of the part length rods of the invention results in a relative increase of in local power of only about 50 percent. For the smaller part length rod motion necessary to control axial xenon oscillation, the relative power increase at the rod tip is larger for the stronger prior art rods (150 percent for the B.sub.4 C rods versus 40 percent for the control rods of the present invention for a 5 percent motion of the part length rod). As a result of the significant differences between the reactivity worth of the prior art length rods and the present part length rod, an accidental drop of the new part length rod 22, 22' becomes an acceptable event as opposed to the accidental drop of a prior art part length rod which was an unacceptable event. As a result of these differences, the prior art part length rods had to be suspended from and controlled by control rod drive mechanisms which were of the non-scrammable type. This required each reactor to be outfitted with two different types of control rod drive mechanisms, one scrammable type for the regular control rods and one non-scrammable type for the part length control rods. As mentioned previously, the new part length control rods permit the use of a single type of control rod drive mechanism which is scrammable. In addition to the reduced cost necessary for outfitting the reactor with only one type of control rod drive mechanism, another advantage is to be gained from a scrammable part length rod. This second advantage is that the new part length rods are readily interchangable with regular control rods so that the positions of the part length control rods may readily be varied according to the requirements established by the management of the fuel cycle. This avoids the extreme difficulty of performing the difficult task of transposition of the drive mechanisms. A further advantage that may be derived from the use of the new part length rod is that, due to the lower effective worth of the new part length rod the effect on power peaking from either removing the part length rod from a core that has been depleted with the part length rods in place of inserting them into a core which has not had part length rods is reduced. This reduces the impact on thermal margin so that smaller thermal margins need be maintained for the purpose of accommodating these two types of part length rod movement. The upper portion 24 of the part length rod preferably consists of pellets of a strong poison, such as boron carbide (B.sub.4 C), contained within a clad or tube of Inconel. In addition the upper portion 24 preferably has a length up to 20 percent of the length of the active region of the core. By limiting the upper portion 24 to 20 percent of the active length of the core, the ability is retained to insert the part length rod 22, 22' up to 80 percent of its length for xenon power oscillation control without adversely effecting the power of the upper end of the core 12 by the insertion of the high worth poison 24. The provision of the upper portion 24 results in a part length control rod which may be scrammed upon the requirement for a rapid shutdown of the reactor. The net effect of scramming such a part length control rod is a contribution in shutdown reactivity rather than an effect which causes a decrease in net shutdown reactivity such as may have occurred upon the dropping of a prior art part length control rod. Accordingly, the available shutdown margin for the entire reactor is increased by the utilization of the part length rods of the present invention.