Computer programs for TRIGA calibration, burnup evaluation, and bookkeeping
Description
Several computer programs have been developed at the University of Arizona to assist the direction and operation of the TRIGA Reactor Laboratory. The programs fall into the following three categories: 1. Programs for calculation of burnup of each fuel element in the reactor core, for maintaining an inventory of fuel element location and fissile content at any time, and for evaluation of the reactivity effects of burnup or proposed fuel element rearrangement in the core. 2. Programs for evaluation, function fitting, and tabulation of control rod measurements. 3. Bookkeeping programs to summarize and tabulate reactor runs and irradiations according to time, energy release, purpose, responsible party, etc. These summarized data are reported in an annual operating report for the facility. The use of these programs has saved innumerable hours of repetitious work, assuring more accurate, objective results, and requiring a minimum of effort to repeat calculations when input data are modified. The programs are written in FORTRAN-IV, and have been used on a CDC-6400 computer. (author)
Files
Additional details
Publishing Information
- Imprint Title
- TRIGA owners' conference 6. Papers and abstracts
- Imprint Pagination
- 204 p.
- Journal Page Range
- p. 5.4-5.10
- Report number
- INIS-US--09N0149
Conference
- Title
- 6. TRIGA owners' conference
- Dates
- 26 Feb - 2 Mar 1978
- Place
- Corvallis, OR (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40029026
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCOUNTING; BURNUP; CALIBRATION; COMPUTER CODES; COMPUTERS; CONTROL ELEMENTS; EDUCATIONAL FACILITIES; FORTRAN; INVENTORIES; IRRADIATION; NUCLEAR FUELS; REACTIVITY; REACTOR CORES; REACTOR OPERATION; TRIGA TYPE REACTORS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MATERIALS; OPERATION; PROGRAMMING LANGUAGES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Abstract on p. xvi-xvii; 2 figs
- Secondary number(s)
- TOC--10