Geri Dön

MTR-Tipi yakıt elemanı kullanılan araştırma reaktörlerinde soğutucu kaybı kazası analizi

Loss of coolent accıdent analysıs for research reactors with MTR type fuel elements

  1. Tez No: 34483
  2. Yazar: BÜLENT SEVDİK
  3. Danışmanlar: PROF.DR. HASBİ YAVUZ
  4. Tez Türü: Doktora
  5. Konular: Nükleer Mühendislik, Nuclear Engineering
  6. Anahtar Kelimeler: Reaktörler, Soğutma, Reactors, Cooling
  7. Yıl: 1994
  8. Dil: Türkçe
  9. Üniversite: İstanbul Teknik Üniversitesi
  10. Enstitü: Nükleer Bilimler Enstitüsü
  11. Ana Bilim Dalı: Belirtilmemiş.
  12. Bilim Dalı: Belirtilmemiş.
  13. 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-

Benzer Tezler

  1. Tez No

    66797

    MTR tipi yakıt elemanı kullanılan araştırma reaktörlerinde soğutucu kanalı tıkanması kazası analizi

    Channel blockage accident analysis for research reractor with MTR type fuel elements

    AYHAN YILMAZER

    Yüksek Lisans

    Türkçe

    Türkçe

    1997

    Nükleer Mühendislikİstanbul Teknik Üniversitesi

    Nükleer Enerji Mühendisliği Ana Bilim Dalı

    PROF. DR. HASBİ YAVUZ

  2. Tez No

    66504

    WGS 84 koordinat sisteminden ülke koordinat sistemine dönüşümler

    Transformations from WGS 84 to ED 50 datum

    Ş.HAKAN KUTOĞLU

    Yüksek Lisans

    Türkçe

    Türkçe

    1997

    Jeodezi ve Fotogrametriİstanbul Teknik Üniversitesi

    Jeodezi ve Fotogrametri Ana Bilim Dalı

    PROF. DR. TEVFİK AYAN

  3. Tez No

    89012

    Penisilinlerin ve Amitriptil'in elektroanalitik incelenmesi

    Electroanalytical investigation of penicilins and amitriptyline

    BENGİ USLU

    Doktora

    Türkçe

    Türkçe

    1999

    Eczacılık ve FarmakolojiAnkara Üniversitesi

    Analitik Kimya Ana Bilim Dalı

    PROF. DR. İNCİ BİRYOL

  4. Tez No

    6107

    Chufa (cyperus esculentus L.) yağ bitkisinin, menemen koşullarında verim ve yağ özellikleri üzerine araştırmalar

    Başlık çevirisi yok

    A.ZİYA SAKINÇ

    Yüksek Lisans

    Türkçe

    Türkçe

    1988

    ZiraatEge Üniversitesi

    Tarla Bitkileri Ana Bilim Dalı

    PROF. DR. ŞÜKRÜ H. EMİROĞLU

Geri Dön