Patent Number: 043057861
Section: description

DESCRIPTION OF THE PREFERRED EMBODIMENT The drawings show an illustrative embodiment of the invention in a storage rack for spent nuclear fuel assemblies. The rack 10 is shown generally in FIG. 1 as comprising a plurality of identical rectangular storage cells 12 which can be aligned with each other in a regular or checkerboard array. The rack 10 is shown alone in FIG. 1 but it will be understood that it is intended to be immersed in a water-filled pit or pool or otherwise filled with water that may or may not contain other chemicals. The cells 12 are all identical and preferably square in cross section and are made of sufficient length to contain the fuel assemblies 14 to be stored. The cells, which are formed from partitions 16, are arranged in a regular array, and are preferably secured together by welding or in any other desired manner to form a modular structure. The cells 12 are preferably made of stainless steel which is a satisfactory structural material and which has the ability to absorb neutrons so that it also serves as a poison material. Any suitable material including those containing deliberate neutron absorbing elements may be used, however, for making the cells. In carrying out the invention, a neutron source may be placed somewhere in the region of a storage rack, such as that of FIG. 1, where the nuclear fuel will eventually be located or the fuel elements themselves may be considered to be the neutron sources. A neutron detector or a series of detectors are placed inside or outside of the storage tank; and the counting rate of neutrons as they arrive at the detectors is observed. The nuclear fuel assemblies are then added to the region one at a time and the counting rate is observed as the fissionable material builds up the multiplication factor of the storage rack. The counting rate detected by the neutron detector follows roughly the well-known subcritical multiplication formula: EQU CR=.alpha..sub.S /(1-k) (1) where: S is the neutron source emission rate; PA1 .alpha. is a term that reflects sensitivity of the detector as well as the attenuation of the neutrons between source and detector, and various geometric considerations to be described later; PA1 CR is the counting rate from the neutron detector and associated electronics; and PA1 k, as before, is the multiplication factor of the assembly at any given time for any given element configuration. A plot, such as the plot of FIG. 2, is usually made of the inverse counting rate, 1/CR, as a function of the number of fuel elements or fuel assemblies added to the storage tank. From this plot, it will be appreciated that the critical point will occur when 1/CR approaches zero. It will be noted from FIG. 2 that for low multiplication factors (i.e., high values of 1/CR), the points appear to be somewhat random. Meaningful predictive information from this plot is not available until high multiplication factors of k greater than approximately 0.9 have been reached. (See Equation (1) above.) Before describing the invention in detail, and by way of background, it will first be assumed that a storage tank for spent fuel assemblies contains a neutron source and a detector, connected to the necessary electronics to form a count rate meter; and that fuel assemblies are being added to the pool one by one. (See FIG. 3.) If a reading is taken on the count rate meter connected to the detector when the multiplication factor is very low (multiplication factor, k, is unknown, but for illustrative purposes is assumed to be 0.1). Then: EQU CR.sub.1 =.alpha..sub.1 S/(1-k.sub.1) (2) where the "1" subscripts refer to this initial reading. Note that if k.sub.1 were zero, .alpha..sub.1 S would be divided by 1, and if k.sub.1 were 0.1,.alpha..sub.1 S would be divided by 0.9, not a large difference in counting rate. The significance of this point is that the first counting rate reading is not particularly sensitive to k.sub.1. Let it be further assumed that more and more fuel assemblies are now loaded into the tank or pool in some fixed geometric pattern, and assume further that it is desirable to stop the loading process at, say, k=0.95. The reading of the counting rate meter can then be represented as: EQU CR.sub.2 =.alpha..sub.2 S/(1-k.sub.2) (3) where the "2" subscripts refer to the second reading after loading is stopped. The ratio of CR.sub.2 /CR.sub.1 can be represented as: EQU CR.sub.2 /CR.sub.1 =(.alpha..sub.2 /.alpha..sub.1).(1-k.sub.1)/(1-k.sub.2) (4) In accordance with the present invention, the value of k.sub.2 is calculated from the foregoing equation; and if k.sub.2 is too close to unity, the loading process is stopped or other modifications are made since criticality is being approached. Assuming that CR.sub.2, CR.sub.1, and k.sub.1 are known, k.sub.2 can be computed from the foregoing equation simply if it is assumed that .alpha..sub.2 /.alpha..sub.1 is unity. As a practical matter, however, .alpha..sub.2 /.alpha..sub.1 is not unity and can vary and depends upon various geometric considerations. There are three principal reasons why the ratio of .alpha..sub.2 to .alpha..sub.1 is not unity. To begin with, the neutron source-to-detector attenuation will vary. This can be illustrated, for example, with the use of FIG. 3 where the numeral 20 designates a storage rack for nuclear fuel assemblies containing a plurality of cells numbered 1 through 14 for the respective fuel assemblies. The neutron source in FIG. 3 is identified by reference numeral 22; while the neutron detector is identified by the reference numeral 24. It will be assumed that the source 22 and detector 24 are initially in place with only water and structural material between them. A fuel assembly is then placed in cell No. 1 in the pool, followed by placing assemblies in cell Nos. 2, 3, 4, etc. From FIG. 3, it is apparent that the neutrons coming from the source must be attenuated differently by each addition of fuel material irrespective of the effective neutron multiplication. The ratio of .alpha..sub.2 to .alpha..sub.1 also varies by virtue of a change in neutron flux distribution as illustrated in FIG. 4. With specific reference to FIG. 4, when a source is placed in the center of a low multiplication region, a neutron flux distribution results in the material that is sharply peaked in the neighborhood of the source and is indicated by curve 26 in FIG. 4. As more and more fissionable material is added to the assembly, the flux distribution changes its shape as indicated by curves 28 and 30 of FIG. 4. Curve 26 results from a low multiplication factor, k, curve 28 results from a higher multiplication factor, and curve 30 results when k is near unity. As the multiplication factor closely approaches unity, the flux distribution shape approaches that of an operating critical reactor. These changes in flux shape affect the reading of a count rate meter whose detector is placed in the vicinity of the assembly. Finally, the ratio of .alpha..sub.2 to .alpha..sub.1 can vary due to changes in detector reading as a function of the loading sequence for nuclear reactor fuel assemblies. Consider, for example, the situation of FIG. 5 where a source 22 within a spent fuel pit 20 is initially symmetrically surrounded by a few fuel elements. The detector 24, for convenience, is shown as being displaced from the pit 20. If it is now desired to add the next element (shown dotted in position 1 or 2 in FIG. 5), the addition of the next element in either position 1 or 2 increases the multiplication factor, k of the assembly by the same amount. Yet, it is obvious that the neutron detector 24 will read differently depending upon whether position 1 or position 2 is loaded next. The physical effect is a combination of the problems previously mentioned; but for ease of correction all effects may be considered to be a function of loading pattern. It will also be apparent that if one were to start building up a fissionable mass in one end of the pool and another fissionable mass in the opposite end of the pool, at some point the two masses will begin to interact and each add to the multiplication factor of the other. Some form of coupling can exist in some types of large reactors and care must be taken that multiple reactors do not exist in the same pool. In accordance with the present invention, the solution for all of these problems begins first by having a rigid loading sequence and pattern for the insertion of spent fuel assemblies into the storage pool. In this manner, the pool is always loaded in exactly the same way. The counting rate, CR, may now be considered as consisting of two parts: A counting rate that is dependent on the amount of fissionable material and poison present, and correction factor to the counting rate, .alpha..sub.2 /.alpha..sub.1, that is essentially only positionally dependent. As each successive element is loaded, the actual counting rate is read, and this information, plus the position of the successive element in the pool, is fed into a small microcomputer or minicomputer associated with the counting rate meter. The computer contains a memory in which is stored the correction factor, .alpha..sub.2 /.alpha..sub.1 for each pool position. The computer then proceeds to calculate and display the multiplication factor, k.sub.2, based on the equation: EQU CR.sub.2 /CR.sub.1 =(.alpha..sub.2 /.alpha..sub.1).(1-k.sub.1)/(1-k.sub.2) To make the correction factors smaller, the first multiplication factor, k, is not measured until a configuration similar to FIG. 3 is reached. In this way, drastic changes in source neutron attenuation are avoided. The correction factors, .alpha..sub.2 /.alpha..sub.1, for each pool position are determined empirically or can be obtained from mathematical considerations with the use of a large computer and sophisticated codes that are well known in the art. It will be noted from FIG. 2, for example, that as k approaches unity, the accuracy of the measurement becomes better, and depends more on the basic multipication factor and less on the correction factor. Alarms and safety devices can be triggered when the calculated counting rate ratio used in the measurement is about twenty, which represents a large safety factor in not allowing a critical loading. The multiple reactor coupling problem can be handled by multiple sources and detectors if the problem is shown to exist theoretically for a given pool design. Such an arrangement, for example, is shown in FIG. 6 where there are three neutron sources 32, 34 and 36 within a fuel storage pool 40 and four neutron detectors 42A, 42B, 42C and 42D. The detectors, in turn, are connected to four count rate meters 44A-44D which produce output electrical signals, each proportional to its associated count rate, which are fed to a small computer 46. This small computer includes a memory wherein the correction factors .alpha..sub.2 /.alpha..sub.1 are stored for each fuel assembly with a given geometrical configuration based upon the assumption that the pool is always loaded in exactly the same way. Also stored in the computer 46 are the count rates obtained after the initial fuel assemblies were inserted into the pool. From these factors, the value of k for each fuel assembly loaded into the pool can be displayed on a display 48; and if k should closely approach unity, an alarm 50 can be actuated. It should be noted that in an installation such as that shown in FIG. 6, the gamma ray environment of the neutron detectors is extremely hostile. Conventional fission counters have been shown to have long lives even in gamma fields up to 10.sup.5 R/hour. As the fields adjacent to a used fuel element immediately after reactor shutdown can be considerably higher than this amount, lead shielding or the like may be provided for the detectors. An efficient detector package would be one that occupies one fuel assembly cell. If this amount of shielding material were shown to be insufficient, however, it may be necessary to restrict moving the elements into the pool until a day or two after reactor shutdown. The sources, such as sources 32-36 shown in FIG. 6 do not have the same problem as the detectors in that they are small, can withstand the environment, and can be placed in suitable positions in the fuel assembly crate lattice. Although the invention has been shown in connection with certain specific embodiments, it will be readily apparent to those skilled in the art that various changes in form and arrangement of parts may be made to suit requirements without departing from the spirit and scope of the invention.