Geri Dön

Shielding design of spent fuel drystorage

Başlık çevirisi mevcut değil.

  1. Tez No: 719398
  2. Yazar: SERHAT UÇAK
  3. Danışmanlar: DOÇ. DR. ZHU Lİ, DOÇ. DR. MEİ Qİ LİANG
  4. Tez Türü: Yüksek Lisans
  5. Konular: Nükleer Mühendislik, Nuclear Engineering
  6. Anahtar Kelimeler: Belirtilmemiş.
  7. Yıl: 2020
  8. Dil: Çince
  9. Üniversite: Tsinghua University
  10. Enstitü: Yurtdışı Enstitü
  11. Ana Bilim Dalı: Belirtilmemiş.
  12. Bilim Dalı: Belirtilmemiş.
  13. Sayfa Sayısı: 40

Özet

Özet yok.

Özet (Çeviri)

Through the development of nuclear energy around the world, spent fuel numbers have increased. When the fuel in the nuclear reactor core becomes inefficient, then it turns into the spent fuel, in this form fuel is no longer needed, therefore there are two ways of handling it, reprocess, or disposal method. Until one of these options is decided, spent fuels must be carefully managed and kept in storage because these spent fuels are still radioactive. Generally, in the nuclear industry, the common method is the pool storage system, which keeps removed spent fuels inside of the water for around 6 years, but, more and more spent fuels means less efficient of safe storage, therefore, dry storage system technologies are under development and getting popular. This thesis focuses on a safe and reliable shielding design of the spent fuel dry storage. As nuclear technologies develop, storage design and technologies also develop alongside it. Spent fuels are among the radiation sources in the nuclear power plant since removed from the reactor core, spent fuels still remain highly radioactive, therefore shielding and sealing these spent fuels are crucial for the environment and people. Design and Calculation are the key parts of the study, while design work is done by using SimpleGeo design software, the calculation is done by using Monte Carlo related Fluka software. Since shielding and protection materials are very important in storage systems, materials have been selected according to the usage level in the industry, in dry storage systems concrete and stainless steel are common and reliable materials. Therefore design has been made by considering these main materials. Spent fuels are placed inside of the cylinder casks made of steel, each cylinder contains 60 spent fuel rods, each rods contain used nuclear fuels that are still radioactive. One of the main advantages of the dry storage system is that does not need power equipment for cooling the fuels, thus during the design air inlet and outlet windows have been put to outer and inner walls. As known, gamma radiation is the hardest to stop, therefore special Z shape has been created between outer and inner walls. After the model is completed, the Fluka method has been used to analyze the neutron and other particle interactions inside and around the model. While design and analysis period, radiation dose limits, inside and around the storage have been considered. This study provides better understanding of the spent fuel dry storage systems, mainly focuses on how to make more safe and reliable storage systems now and the future. The model based Abstract III on the real data and active dry storage system and only has storage purpose. The spent fuel dry storage systems provide, safe, easy and convenient storage of the used fuels, the importance and benefits of the dry storage should not be neglected. The dry storage technologies include; single, dual, multi-purpose casks and canisters. Some of the casks can be used for transportation due to their design and construction. All of the designs have the same purpose, that is protecting the environment and people from the dangerous spent fuel radiation, and shielding the radiation. Through the years many have been developed and still getting developed, the spent fuel dry storage systems have become an inseparable part of nuclear industry.

Benzer Tezler

  1. Hızlandırıcı güdümlü sistemlerin nötronik tasarımı:Hızlandırıcı zırhlama, reaktör güvenliği sorunu ve radyoaktif kaynak terimleri

    Neutronic design of accelerator driven systems: Accelerator shielding, reactor safety issues and radioactive source terms

    YURDUNAZ ÇELİK

    Doktora

    Türkçe

    Türkçe

    2016

    Fizik ve Fizik MühendisliğiGazi Üniversitesi

    Fizik Ana Bilim Dalı

    PROF. DR. BAŞAR ŞARER

  2. Otomatik üretim kontrolü sistemlerine yapılan yanlış veri enjeksiyon saldırılarının torbalama ağaçları algoritması ile tespiti

    Detection of false data injection attacks on automatic generation control systems with bagged trees algorithm

    ATAKAN ÖZTÜRK

    Yüksek Lisans

    Türkçe

    Türkçe

    2023

    Elektrik ve Elektronik Mühendisliğiİstanbul Teknik Üniversitesi

    Elektrik Mühendisliği Ana Bilim Dalı

    PROF. DR. VEYSEL MURAT İSTEMİHAN GENÇ

  3. Atıkların yüksek sıcaklıkta sürekli pirolizi için yarı-pilot ölçek yeni bir vidalı reaktör geliştirilmesi

    Development of a new semi-pilot scale screw reactor for continuous pyrolysis of wastes at high temperature

    ANIL ÜNSAÇ

    Doktora

    Türkçe

    Türkçe

    2024

    Enerjiİstanbul Teknik Üniversitesi

    Enerji Bilim ve Teknoloji Ana Bilim Dalı

    PROF. DR. NİLGÜN YAVUZ

    PROF. DR. HASAN CAN OKUTAN

  4. Electro-smog mitigation for achieving healthy buildings: Investigating the relationship between architectural design parameters and EMR levels

    Sağlıklı bina hedefiyle elektro-sisin azaltılması: Mimari tasarım parametreleri ve EMR seviyeleri arasındaki ilişkinin incelenmesi

    BUĞRA TETİK

    Doktora

    İngilizce

    İngilizce

    2023

    MimarlıkOrta Doğu Teknik Üniversitesi

    Mimarlık Ana Bilim Dalı

    PROF. DR. SOOFIA TAHIRA ELIAS ÖZKAN

  5. Fantom malzemelerinin doku denkliğinin deneysel ve teorik olarak incelenmesi

    Experimental and theoretical investigation of tissue equivalency for phantom materials

    İREM ERK

    Yüksek Lisans

    Türkçe

    Türkçe

    2016

    Radyoloji ve Nükleer Tıpİstanbul Teknik Üniversitesi

    Nükleer Araştırmalar Ana Bilim Dalı

    PROF. DR. NESRİN ALTINSOY