Design method for fast reactor mixed uranium plutonium fuel component control

A technology of fuel composition and design method, applied in the directions of reactor fuel elements, reactor fuel materials, computer-aided design, etc., can solve the problems of component power change, affecting the temperature distribution of the outlet coolant, and large impact, and achieve the effect of reducing the impact.

Pending Publication Date: 2021-04-06
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Among them, the core power distribution is the main one that has a greater impact and cannot be adjusted by conventional means.
Direct use of plutonium from different sources will lead to significant changes in component power, affect the outlet coolant temperature distribution, and may even exceed the fuel element line power limit, affecting reactor safety

Method used

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  • Design method for fast reactor mixed uranium plutonium fuel component control
  • Design method for fast reactor mixed uranium plutonium fuel component control
  • Design method for fast reactor mixed uranium plutonium fuel component control

Examples

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Embodiment 1

[0054] In the present embodiment, the method of the present invention is specifically described by taking mixed uranium plutonium oxide fuel (MOX) as an example, as figure 1 , figure 2 As shown, the method includes the following steps:

[0055] (1) Core design calculation, specifically including the following steps:

[0056] A. Determine the PuO used in the core material 2 The nominal composition of the powder, namely PuO 2 The types of industrial plutonium isotopes of powder and the mass percentages of each industrial plutonium isotope are used as the core design input, and the plutonium equivalent weight factors of each industrial plutonium isotope are calculated; according to the mass percentage of each industrial plutonium isotope and its plutonium equivalent weight factor, the Get PuO 2 The plutonium equivalent design value of the powder;

[0057] In mixed uranium-plutonium fueled fast reactors, 239 Pu is the main fissile nuclide and can be used 239 Pu is used as ...

Embodiment 2

[0085] Fuel Design Calculation for the First Fuel of a MOX Fueled Fast Reactor

[0086] Taking a 600,000-kilowatt sodium-cooled MOX fuel fast reactor as an example, the reactor core is designed with a rated thermal power of 1,500 MW. The reactor uses MOX fuel, in which industrial plutonium comes from the reprocessing of spent fuel from pressurized water reactors, and depleted uranium is used for uranium. The coolant uses liquid metal sodium. The balanced state core is loaded with 348 boxes of MOX fuel assemblies, which are divided into inner, middle and outer regions according to different enrichment degrees. Since the industrial plutonium in the MOX fuel is planned to come from the industrial plutonium in the spent fuel of the PWR recovered by the reprocessing plant, the balanced core design is carried out based on the nominal plutonium composition given by the reprocessing plant, and the plutonium in the MOX fuel in each zone is determined The uranium composition ratio, wh...

Embodiment 3

[0098] A million-kilowatt class sodium-cooled MOX fuel core is selected as an example. In order to flatten the power distribution of the core, the fuel assemblies are divided into inner, middle and outer zones according to the degree of enrichment, and the number of fuel assemblies loaded in the three zones are 211, 156 and 174 respectively. The core control rod system consists of 30 control rods, including 2 adjustment rods, 3 passive safety rods, 9 safety rods and 16 compensation rods. When designing the core, consider PuO 2 The plutonium isotopic composition of the powder is a definite value (namely the nominal value), and the adjustment of the enrichment of the fuel in the inner, middle and outer regions is by changing the PuO 2 Powder and Depleted UO 2 The proportion of powder to achieve. The design value of the industrial plutonium isotopic composition of the core fuel of the first furnace is shown in Table 4, and this fuel composition is the target composition of mix...

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Abstract

The invention relates to a fast reactor mixed uranium plutonium fuel component control design method, which comprises the following steps of (1) reactor core design calculation: calculating plutonium equivalent design values in mixed uranium plutonium fuel; determining a plutonium equivalent target value of the mixed uranium plutonium fuel; calculating the mass parts of Pu and U components (such as PuO2 powder and UO2 powder in mixed uranium plutonium oxide fuel MOX) in the mixed uranium plutonium fuel according to the plutonium equivalent target value; (2) selecting a required quantity of raw materials of which the plutonium equivalent value is close to the plutonium equivalent design value in the step (1); (3) performing plutonium raw material mixed abundance on the selected raw materials to obtain mixed abundance Pu raw material powder; and (4) preparing a mixed uranium plutonium fuel pellet / core body. The design method provided by the invention can solve the problem that the plutonium isotope component difference affects the design parameters of the reactor core of the uranium-plutonium mixed fuel fast reactor, especially the component power distribution.

Description

technical field [0001] The invention belongs to the technical field of nuclear power design, and in particular relates to a design method for controlling the composition of fast reactor mixed uranium-plutonium fuel. Background technique [0002] Fast neutron reactors (referred to as fast reactors) refer to nuclear reactors in which fast neutrons trigger a chain fission reaction. The fast reactor has the remarkable characteristics of being able to multiply nuclear fuel and transmute long-lived nuclear waste, and is the main reactor type of the fourth-generation nuclear energy system. In order to effectively utilize natural uranium resources and improve fuel multiplication capabilities, the most typical fuel choice for fast reactors is mixed uranium and plutonium fuel. The form of mixed uranium-plutonium fuel can be mixed uranium-plutonium oxide fuel (MOX, such as French Phoenix, Super Phoenix fast reactor and Russian BN-800 fast reactor driving fuel, etc.), mixed uranium-plu...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C21/02G21C3/62G06F30/20G06F119/18
CPCG21C21/02G21C3/623G06F30/20G06F2119/18Y02E30/30
Inventor 胡赟徐李杨勇张坚单浩栋霍兴凯曹攀陈仪煜
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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