MTR-Tipi yakıt elemanı kullanılan araştırma reaktörlerinde soğutucu kaybı kazası analizi
Loss of coolent accıdent analysıs for research reactors with MTR type fuel elements
- Tez No: 34483
- Danışmanlar: PROF.DR. HASBİ YAVUZ
- Tez Türü: Doktora
- Konular: Nükleer Mühendislik, Nuclear Engineering
- Anahtar Kelimeler: Reaktörler, Soğutma, Reactors, Cooling
- Yıl: 1994
- Dil: Türkçe
- Üniversite: İstanbul Teknik Üniversitesi
- Enstitü: Nükleer Bilimler Enstitüsü
- Ana Bilim Dalı: Belirtilmemiş.
- Bilim Dalı: Belirtilmemiş.
- Sayfa Sayısı: Belirtilmemiş.
Özet
By considering this assumption, the half value of the residual decay heat was used for the simulation of the experiments on the code. For the long cooling time around one day, the short lived fission products with high energy gammas will decay and the contribution of the high energy gammas to the decay heat will decrease. Credit for this effect must be taken here for the calculation done with long cooling time period. For the whole core“LOCA”analysis this effect for the residual decay heat can be neglected because of the interference between the fuel elements. In spite of the uncertainties in the calculation of the residual decay heat, the experimental and theoretical results were in agreement. In the third step of the study, whole core“LOCA”analysis of the TR-2 Research Reactor was done by THEAP-I for the 35, 20, 45, 60 minutes cooling times. The calculated plate temperatures are given in the tables. The effects of the initial plate temperatures on the maximum plate temperatures were also analyzed and it was seen that there were no significant increase in the maximum plate temperature with the increase, of the initial plate temperature. The detailed information about the THEAP-I code, such as problem modelling and definition, heat transfer coefficient and correlations, computation methods and necessary data for the input files are given in the thesis. -XII-
Özet (Çeviri)
The results of the theoretical and experimental studies done in this work show that, THEAP-I code is a reliable computer program for the“LOCA”analysis of the research reactors with MTR-type fuel elements. The experimental, results obtained in this study will be very useful for the sensitivity analysis of the computational methods used for“LOCA ”analysis. Study on the partial coverage of the core, for two- phase flow conditions can be carried out as the next step of this study. -XIII-By considering this assumption, the half value of the residual decay heat was used for the simulation of the experiments on the code. For the long cooling time around one day, the short lived fission products with high energy gammas will decay and the contribution of the high energy gammas to the decay heat will decrease. Credit for this effect must be taken here for the calculation done with long cooling time period. For the whole core“LOCA”analysis this effect for the residual decay heat can be neglected because of the interference between the fuel elements. In spite of the uncertainties in the calculation of the residual decay heat, the experimental and theoretical results were in agreement. In the third step of the study, whole core“LOCA”analysis of the TR-2 Research Reactor was done by THEAP-I for the 35, 20, 45, 60 minutes cooling times. The calculated plate temperatures are given in the tables. The effects of the initial plate temperatures on the maximum plate temperatures were also analyzed and it was seen that there were no significant increase in the maximum plate temperature with the increase, of the initial plate temperature. The detailed information about the THEAP-I code, such as problem modelling and definition, heat transfer coefficient and correlations, computation methods and necessary data for the input files are given in the thesis. -XII-The results of the theoretical and experimental studies done in this work show that, THEAP-I code is a reliable computer program for the“LOCA”analysis of the research reactors with MTR-type fuel elements. The experimental, results obtained in this study will be very useful for the sensitivity analysis of the computational methods used for“LOCA ”analysis. Study on the partial coverage of the core, for two- phase flow conditions can be carried out as the next step of this study. -XIII-By considering this assumption, the half value of the residual decay heat was used for the simulation of the experiments on the code. For the long cooling time around one day, the short lived fission products with high energy gammas will decay and the contribution of the high energy gammas to the decay heat will decrease. Credit for this effect must be taken here for the calculation done with long cooling time period. For the whole core“LOCA”analysis this effect for the residual decay heat can be neglected because of the interference between the fuel elements. In spite of the uncertainties in the calculation of the residual decay heat, the experimental and theoretical results were in agreement. In the third step of the study, whole core“LOCA”analysis of the TR-2 Research Reactor was done by THEAP-I for the 35, 20, 45, 60 minutes cooling times. The calculated plate temperatures are given in the tables. The effects of the initial plate temperatures on the maximum plate temperatures were also analyzed and it was seen that there were no significant increase in the maximum plate temperature with the increase, of the initial plate temperature. The detailed information about the THEAP-I code, such as problem modelling and definition, heat transfer coefficient and correlations, computation methods and necessary data for the input files are given in the thesis. -XII-The results of the theoretical and experimental studies done in this work show that, THEAP-I code is a reliable computer program for the“LOCA”analysis of the research reactors with MTR-type fuel elements. The experimental, results obtained in this study will be very useful for the sensitivity analysis of the computational methods used for“LOCA ”analysis. Study on the partial coverage of the core, for two- phase flow conditions can be carried out as the next step of this study. -XIII-
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