Reactor shielding design of smart small modular reactor (SMR)using mcbend Monte Carlo code
SMART Küçük Modüler Reaktörünün (SMR) McBend Monte Carlo Kodu Kullanarak Reaktör Zırhlama Tasarımı
- Tez No: 770547
- Danışmanlar: Belirtilmemiş.
- Tez Türü: Yüksek Lisans
- Konular: Astronomi ve Uzay Bilimleri, Bilim ve Teknoloji, Fizik ve Fizik Mühendisliği, Astronomy and Space Sciences, Science and Technology, Physics and Physics Engineering
- Anahtar Kelimeler: Belirtilmemiş.
- Yıl: 2020
- Dil: İngilizce
- Üniversite: The University of Birmingham
- Enstitü: Yurtdışı Enstitü
- Ana Bilim Dalı: Belirtilmemiş.
- Bilim Dalı: Belirtilmemiş.
- Sayfa Sayısı: 46
Özet
During the last 70 years, nuclear power has already been a significant source worldwide and future modules of reactors of Gen IV could procure carbon-free, reliable and safe energy in a compact modular design to a more sustainable future. This thesis aims to evaluate the impact of SMRs in the energy field, focusing on the design applicability and radiation protection. In order to predict a simulated worker's dose rate, the Monte Carlo Simulation Approach (Mcbend) was used on the SMART reactor design which is a small-medium modular reactor. The simulation's result showed, to minimise neutron radiation well under limits (20 mSv/yr or 0.01 mSv/hr), that the shielding given by the reactor vessels is adequate. Furthermore, it is deduced that, for the SMART and equivalent SMR reactors, there is no increased risk of radiation for the population. 2.14 density concrete with boron has a better dose result. For without boron 2.20 density concrete has better dose rate result. About stainless steel, 40 cm thickness of steel was observed has a good result. Changing concrete thickness, 60 cm concrete has better dose rate result. As a shielding material, borate concrete was observed a good material for this SMART reactor
Özet (Çeviri)
Özet çevirisi mevcut değil.
Benzer Tezler
- 600 MWe gücünde PWR tipi bir nükleer reaktör kalp öndizayn analizi
Başlık çevirisi yok
FARZAD REZAEİ BASHARAT
- Nükleer reaktörlerde alternatif nötron zırhlama malzemelerinin teorik geliştirilmesi
Theoretical development of alternative neutron armoring materials in nuclear reactors
MEHMET SADIK TANDOĞAN
Yüksek Lisans
Türkçe
2022
Nükleer MühendislikSinop ÜniversitesiDisiplinlerarası Nükleer Enerji ve Enerji Sistemleri Ana Bilim Dalı
DOÇ. DR. HASAN OĞUL
- Gama geçirgenlik prensibi ile malzemelerin ağırlıklarının ölçülmesi
Weight measurements by using gama transmission principle
S.ÜNAL ÖZTÜRK
Yüksek Lisans
Türkçe
1997
Nükleer Mühendislikİstanbul Teknik ÜniversitesiElektrik Mühendisliği Ana Bilim Dalı
PROF. DR. ALİ NEZİHİ BİLGE
- Gama geçirgenlik tekniği ile yoğunluk tayini
Density measurements by using gama transmission technique
NESLİHAN BALTACIOĞLU
