Ergimiş tuz reaktörlerinde (MSR) risk analizleri
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Tarih
2024
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Sinop Üniversitesi
Erişim Hakkı
info:eu-repo/semantics/openAccess
Özet
Bu çalışmada ergimiş tuz reaktörleri için olasılığa dayalı risk analizi yöntemi kullanılarak güvenilirlik değerlendirmesi yapılmıştır. Yakıt tuzu tahliye sistemi, atık ısı uzaklaştırma sistemi ve off-gaz sistemleri şematik olarak gösterilerek güvenilirlik değerleri hesaplanmıştır. Hesaplamalarda kullanılan bileşen güvenilirlikleri ticari olarak kullanılan reaktör türlerindeki benzer yapı ve göreve sahip bileşenlerden elde edilmiştir. Her bir sistem için hata ağacı analizi yapılarak güvenilirlikler hesaplanmıştır. Yakıt tuzu tahliye sistemi için güvenilirlik değeri 0,9487 olarak bulunmuştur. Atık ısı giderme sistemi için güvenilirlik 0,8731 olarak bulunmuştur. Off-gaz sistemi için güvenilirlik 0,7833 olarak elde edilmiştir. Reaktörün muhafaza sistemleri için güvenilirlikler literatürdeki benzer zırhlama bariyerlerinden elde edilmiş ve sırasıyla birincil muhafaza bariyeri için 0,9999, ikincil muhafaza bariyeri için 0,9999 ve reaktör binası için 0,999999 olarak bulunmuştur. Tüm sistemler için elde edilen güvenilirlik değerleri kaynar su reaktörlerinde bulunan güvenlik sistemlerinin güvenilirlik değerleri ile karşılaştırıldığında yakıt tuzu tahliye sistemi, birincil muhafaza bariyeri, ikincil muhafaza bariyeri ve reaktör binası için hesaplanan güvenilirlik değerlerinin kaynar su reaktörü güvenlik sistemi değerlerine yakın ve makul değerlerde olduğu görülmüştür. Atık ısı giderme sistemi ve off-gaz sistemi için hesaplanan güvenilirlik değerlerinin kaynar su reaktörlerinin güvenlik sistemi değerlerine göre düşük olduğu görülmüştür. Pompa kazası ve fisyon ürünü salınımı başlangıç olayları için olay ağacı analizi yapılmıştır. Pompa kazasına karşı başarı oranı 0,9999 olarak bulunmuştur. Fisyon ürünü salınımına karşı başarı oranı 0,9999 olarak elde edilmiştir. Ergimiş tuz reaktörleri için güvenlik sistemi tasarımlarının geliştirilmesi gerektiği görülmüştür. Kaza durumunda reaktörün korunmasının derinliğine savunma prensibine uygun olarak art arda eklenen sistemler ile sağlandığı görülmektedir.
In this study, reliability assessment was performed for molten salt reactors using probabilistic risk analysis method. Fuel salt drain system, heat removal system and off-gas systems were shown schematically and reliability values were calculated. Component reliabilities used in calculations were obtained from components with similar structures and functions in commercially used reactor types. Reliabilities were calculated by performing fault tree analysis for each system. Reliability value for fuel salt drain system was found as 0.9487. Reliability for heat removal system was found as 0.8731. Reliability for off-gas system was obtained as 0.7833. Reliabilities for containment systems of reactor were obtained from similar armor barriers in literature and were found as 0.9999 for primary containment barrier, 0.9999 for secondary containment barrier and 0.999999 for reactor building, respectively. When the reliability values obtained for all systems are compared with the reliability values of the safety systems in boiling water reactors, it is seen that the reliability values calculated for the fuel salt drain system, primary containment barrier, secondary containment barrier and reactor building are close to the boiling water reactor safety system values and at reasonable values. It is seen that the reliability values calculated for the heat removal system and off-gas system are lower than the safety system values of boiling water reactors. An event tree analysis was performed for the pump accident and fission product release initial events. The success rate against pump accident was found to be 0.9999. The success rate against fission product release was obtained as 0.9999. It was seen that the safety system designs for molten salt reactors should be improved. It is seen that the protection of the reactor in case of an accident is provided by successively added systems in accordance with the defense in depth principle.
In this study, reliability assessment was performed for molten salt reactors using probabilistic risk analysis method. Fuel salt drain system, heat removal system and off-gas systems were shown schematically and reliability values were calculated. Component reliabilities used in calculations were obtained from components with similar structures and functions in commercially used reactor types. Reliabilities were calculated by performing fault tree analysis for each system. Reliability value for fuel salt drain system was found as 0.9487. Reliability for heat removal system was found as 0.8731. Reliability for off-gas system was obtained as 0.7833. Reliabilities for containment systems of reactor were obtained from similar armor barriers in literature and were found as 0.9999 for primary containment barrier, 0.9999 for secondary containment barrier and 0.999999 for reactor building, respectively. When the reliability values obtained for all systems are compared with the reliability values of the safety systems in boiling water reactors, it is seen that the reliability values calculated for the fuel salt drain system, primary containment barrier, secondary containment barrier and reactor building are close to the boiling water reactor safety system values and at reasonable values. It is seen that the reliability values calculated for the heat removal system and off-gas system are lower than the safety system values of boiling water reactors. An event tree analysis was performed for the pump accident and fission product release initial events. The success rate against pump accident was found to be 0.9999. The success rate against fission product release was obtained as 0.9999. It was seen that the safety system designs for molten salt reactors should be improved. It is seen that the protection of the reactor in case of an accident is provided by successively added systems in accordance with the defense in depth principle.
Açıklama
Anahtar Kelimeler
Nükleer Mühendislik, Nuclear Engineering
