This report has been prepared to provide instructional material on the use of BREED and its user-oriented procedures to facilitate computer automation of design calculations. The input deck completely identifies and controls the calculational sequence needed to produce a desired end product. The input/output data processing is achieved with BREED by using a set of simple, easily understood user commands, usually short descriptive words, which the user inserts in his input deck. Data processing within a technical more » discipline and data transfer between technical disciplines can be accommodated. The automation that can be achieved as a result of using BREED significantly reduces not only the time required for data preparation and hand transfer of data, but also the time required to complete an iteration of the total design effort. It provides the capability to interface different application programs into a single computer run to provide a complete design function. (37 references) (auth) « lessīREED is an executive CDC-7600 program which was developed to facilitate the sequence of calculations and movement of data through a prescribed series of breeder reactor design computer programs in an uninterrupted single-job mode. Sample problems have been run on the IBM 360/75 computer. Some of these routines are necessary and, if other computers are used must be rewritten for those computers. Special timing and input-output routines are available and used by the RELAP4 program for the IBM 360 systems. RELAP4 source decks are available in double precision (EBCDIC) versions. By simply increasing the array sizes, these limits could be raised, if necessary, until the capacity of the particular computer is reached.
Currently, the number of these control volumes is limited to 75 and the number of junctions (flow paths) between volumes is limited to 100. RELAP4 then solves an integral form of the fluid conservation and state equations applied to each user-defined control volume. The RELAP4 user must define the geometric features of the system to be analyzed as well as an appropriate set of initial conditions. In addition to describing transients in boiling- water and pressurized-water reactors, the program is sufficiently versatile to describe transients in experimental more » thermal-hydraulic systems. The program also calculates reactor power, decay heat, and reactivity.
The program calculates fluid conditions such as flow, pressure, mass inventory, and quality thermal conditions such as surface temperatures, temperature profiles, and energy distributions and heat fluxes in power generating and dissipating elements. RELAP4 is a digital computer program, written in FORTRAN IV, developed to describe the behavior of water-cooled nuclear reactors subjected to postulated transients such as those resulting from loss of coolant, pump failure, or power excursions.
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