PULSTRI-1 computer program for mixed core pulse calculation
Description
PUISTRI-1 is a computer code designed for calculations of the pulse parameters of TRIGA Mark II reactor with mixed core. The code is provided with data for four types of fuel elements: standard 8.5 and 12 w/o, LEU and FLIP. The pulse parameters, such as maximum power, prompt pulse energy and average fuel temperatures are calculated in adiabatic point kinetics, approximation, modified by taking into account temperature dependence of fuel temperature reactivity coefficient and thermal capacity factor averaged over all elements in the core. Maximal fuel temperature at power peaking location is calculated from total released energy using total power peaking factor and heat capacity of the element at the location of the power peaking. Results of the code were compared to data found in references (mainly General Atomics safety analysis reports) showing good agreement for all main pulse parameters. The most important parameters, average and maximal fuel temperature, are found to be systematically slightly overpredicted (20 C and 50 C, respectively). Other parameters (energy, peak power, width) agree within ± 10 % to the reference values. The code is written in FORTRAN for IBM PC computer. The input is user friendly. running time of IBM PC AT is a few seconds. It is designed for practical applications in pulse experiments as an analytical tool for predicting pulse parameters. (orig.)
Additional details
Publishing Information
- Imprint Title
- Eleventh European TRIGA users conference. Papers and abstracts
- Imprint Pagination
- 416 p.
- Journal Page Range
- 12 p.
Conference
- Title
- 11. European TRIGA Users Conference
- Dates
- 11-13 Sep 1990
- Place
- Heidelberg (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 39121932
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; FORTRAN; FUEL ELEMENTS; IBM COMPUTERS; P CODES; PERSONAL COMPUTERS; PULSES; REACTIVITY COEFFICIENTS; REACTOR CORES; REACTOR KINETICS; SPECIFIC HEAT; TEMPERATURE DEPENDENCE; TRIGA-2 REACTOR
- Descriptors DEC
- COMPUTER CODES; COMPUTERS; DIGITAL COMPUTERS; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; KINETICS; MICROCOMPUTERS; PHYSICAL PROPERTIES; PROGRAMMING LANGUAGES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS