Analysis of thermal reliability of the RA reactor
Creators
- 1. Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)
Description
In the first part the basic elements of mathematical method used in further analysis are presented. The method offers the possibility for performance of an analysis of one or more quantities that are essential for thermic reliability on the basis of statistical data from reactor exploitation. This method could be used to determine the character of their behaviour, to analyze fluctuation around the mean and nominal values, to determine the probabilities of attaining and exceeding certain limits etc., these values being then compared with calculation and critical. In the second part of the paper the method is applied to the analysis of the fuel can temperature of reactor RA in Vinca. Two-year exploitation period has been observed at nominal power of 6,5 MW. The actual state of temperature compared with the values from the project indicates certain deviations which expressed over the probability give a factor of reliability in work of some fuel channels and zones. In the conclusion it is pointed out the possibility of application of the described methods in the safety analyses of reactor systems, and the purpose of application is realization of a more real solution, also obtaining of a more real picture regarding thermal reliability state (author)
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of nuclear sciences Vinca, Paper presented at International congress on the diffusion of fission products. Saclay, France, 1969.Abstract (Serbian)
U prvom delu prikazani su osnovni elementi matematickog metoda koji se koristi u daljoj analizi. Metod omogucava da se na bazi statistickih podataka iz eksploatacije reaktora izvrsi analiza jedne iii vise ve1icina bitnih za termicku pouzdanost. Metodom se utvrdjuje karakter njihovog ponasanja, analiziraju fluktuacije oko srednjih i nominalnih vrednosti, odredjuju verovatnoce dostizanja i premasivanja odredjenih granica i dr., pa se te vrednosti uporedjuju sa proracunskim i kriticnim. U drugom delu rada metod je primenjen na analizu temperature kosu1jice goriva reaktora RA u Vinci. Posmatran je dvogodisnji eksploatacioni period rada na nominalnoj snazi od 6,5 MW. Stvarno stanje temperature uporedjeno sa vrednostima iz projekta pokazuje odredjena odstupanja, koja izrazena preko verovatnoce daju stepen pouzdanosti rada pojedinih gorivnih kanala i zona. U zakljucku se ukazuje na mogucnosti primene izlozenog metoda u analizama sigurnosti reaktorskih sistema, a cilj primene je ostvarenje realnijih resenja, dobijanje realnije slike stanja termicke pouzdanosti (author)Files
38013812.pdf
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Additional details
Additional titles
- Original title (Serbian)
- Analiza termicke pouzdanosti jezgra reaktora RA
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- INIS-RS--0090
INIS
- Country of Publication
- Serbia
- Country of Input or Organization
- Serbia
- INIS RN
- 38013812
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FUEL CHANNELS; MATHEMATICAL MODELS; R-A REACTOR; RELIABILITY; TEMPERATURE DISTRIBUTION; THERMAL ANALYSIS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 5 refs, 1 tab, 3 figs
- Secondary number(s)
- IBK--875