DSNP; dynamic simulation nuclear power plants. [IBM370; FORTRAN IV and DSNP]

Technical Report ·

OSTI ID:6343381

Saphier, D

DSNP (Dynamic Simulator for Nuclear Power-Plants) is a system of programs and data files by which a nuclear power plant, or part thereof, can be simulated. The acronym DSNP is used interchangeably for the DSNP language, the DSNP libraries, the DSNP precompiler, and the DSNP document generator. The DSNP language is a special-purpose, block-oriented digital-simulation language developed to facilitate the preparation of dynamic simulations of a large variety of nuclear power plants. It is a user-oriented language that permits the user to prepare simulation programs directly from power plant block diagrams and flow charts by recognizing the symbolic DSNP statements for the appropriate physical components and listing these statements in a logical sequence according to the flow of physical properties in the simulated power plant. Physical components of nuclear power plants are represented by functional blocks, or modules. The nuclear reactor, for example, has a kinetic module, a power distribution module, a feedback module, a thermodynamic module, a hydraulic module, and a radioactive heat decay module. Basic functional blocks such as integrators, pipes, function generators, connectors, and many auxiliary functions representing properties of materials used in nuclear power plants are also available. The DSNP precompiler analyzes the DSNP simulation program, performs the appropriate translations, inserts the requested modules from the library, links these modules together, searches necessary data files, and produces a simulation program in FORTRAN. IBM370; FORTRAN IV and DSNP; OS/370; 240K bytes of storage are required to compile and translate a typical power plant simulation program. Six scratch files require disk or fast magnetic tape storage and a permanent library file unit is used. All sample problems were executed in a 250K byte or smaller region.

• Research Organization: Argonne National Lab., IL (USA)
• OSTI ID: 6343381
• Report Number(s): ANL/NESC-784; ON: DE83048784
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
D CODES
FORTRAN
IBM COMPUTERS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROGRAMMING LANGUAGES
SIMULATION
THERMAL POWER PLANTS