Heat pipe reactor lifetime optimization and conceptual core design
Isı borusu reaktörü ömür optimizasyonu ve kavramsal çekirdek tasarımı
- Tez No: 840472
- Danışmanlar: PROF. SUN JUN, DR. TANG CHUNTAO
- Tez Türü: Yüksek Lisans
- Konular: Enerji, Energy
- Anahtar Kelimeler: Neutronic analysis, thermal hydraulic analysis, heat pipe reactor, micro reactor, core design
- Yıl: 2023
- Dil: İngilizce
- Üniversite: Tsinghua University
- Enstitü: Yurtdışı Enstitü
- Ana Bilim Dalı: Belirtilmemiş.
- Bilim Dalı: Belirtilmemiş.
- Sayfa Sayısı: 90
Özet
Current nuclear power plant installations take years to plan and construct. They are long-term, wide and complex projects. A large portion of the total cost of these reactors is caused by the initial costs and construction expenses. Even though the increasing lifetimes and reactor powers make nuclear reactors favorable, the initial costs need to be decreased to make nuclear power more competitive. Small and micro modular reactors are potentially able to defy these negative results. They can remove the long and complex construction process of nuclear reactor installations in the future. A heat pipe micro reactor is a type of reactor that is built on a small or micro scale. It can possibly be commissioned easily when compared to larger reactor projects. By considering its other advantages, such as applicability in remote locations and space applications, the research on heat pipe reactors has increased in number in recent years. A heat pipe reactor is a type of nuclear reactor that does not have a coolant actively pumped into the core. The reactor core has fixed heat pipes in its cavities. The heat pipe cooled reactor is a unique type of reactor that removes the heat of the core by utilizing heat pipe components. When compared to standard reactors, it has important modifications in core structure, coolant, and material, entirely changing the geometric architecture of the reactor core. Main pipelines, circulating pump and auxiliary pumping equipment have been eliminated in this design, which can potentially decrease the reactor cost. The core and the electricity generation components have no coolant flow. The core heat is transferred by uniformly located heat pipes. The core of the reactor is assembled using solid fuel rods. The reactor core is primarily composed of heat pipes, fuel rods, structural blocks to hold the assemblies, the reflector and control elements. The most cited heat pipe reactor designs in the literature focus on reliability and manufacturability. Even though they make the creation process much easier, these works are specific applications with previously specified powers and lifetime limits. These papers miss the power, lifetime, fuel efficiency and enrichment optimization, that are necessary for commercial applications. The target of this thesis is to research the design parameters of the heat pipe reactor cores in order to find designs with a long lifetime, low enrichment, high power and high fuel efficiency. For improving the existing reactor cores, different heat pipe reactor designs have been investigated. Core length, fuel type, reflector ABSTRACT III thickness, reflector compound, using unequal fuel enrichment at different positions, moderating the neutron flux and using initial neutron poison have been researched for increasing the lifetime, burnup and decreasing the necessary enrichment. Heat pipe diameter and core width were investigated to increase the core power. Reflector compound, fuel compound, core length and core diameter have been found as the parameters that affect the lifetime and fuel efficiency most. The heat pipe fluid, heat pipe wall material, filling medium material selections are more connected to heat transfer properties and these aren't investigated. By using the insight from the parametric analyses and previous heat pipe reactor designs, a new 28 MWt long-lifetime core design has been proposed with increased lifetime and increased power. The fuel mass change and core lifetime, control drum reactivity worth, radial power distribution, negative temperature coefficient, total burnup and neutron poison buildup of the proposed design have been investigated. Heat pipe temperature and fuel temperature of the design have been analyzed.
Özet (Çeviri)
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