Sodium-void reactivity measurement method for sodium-cooled fast reactor and sodium-void experimental assembly

A technology of sodium-cooled fast reactor and measurement method, which is applied in the direction of reactor, nuclear reactor monitoring, fuel element, etc., can solve the problems of measurement result error, different sealing methods, backward measurement and control technology, etc.

Active Publication Date: 2012-12-05
CHINA INSTITUTE OF ATOMIC ENERGY
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Problems solved by technology

In the 1960s and 1970s, foreign experimental fast reactors used special test channels to move sodium cavities, and sodium cavitation test components replaced fuel components to measure the reactivity of sodium cavitation. Due to the different structures o

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  • Sodium-void reactivity measurement method for sodium-cooled fast reactor and sodium-void experimental assembly
  • Sodium-void reactivity measurement method for sodium-cooled fast reactor and sodium-void experimental assembly
  • Sodium-void reactivity measurement method for sodium-cooled fast reactor and sodium-void experimental assembly

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[0020] The present invention will be further described below in conjunction with the drawings and specific embodiments.

[0021] The following takes the China Experimental Fast Reactor as an example to illustrate the provided method for measuring the sodium cavitation reactivity value of the sodium-cooled fast reactor. Before describing the measurement method of the present invention in detail, a brief description of the fuel assembly and sodium cavitation test assembly used in the measurement will be explained.

[0022] The fuel assembly used by the China Experimental Fast Reactor generally includes a fuel element rod area and upper and lower pipe seats located on and below the fuel element rod area. The fuel element rod area 2 includes bundles of fuel elements fixed on a grid plate 23. The rod 21 and the outer hexagonal tube 22 containing the rod bundle. The fuel element rod 21 is a thin rod made of a cladding tube filled with uranium oxide material pellets, arranged in a triang...

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Abstract

The invention relates to a sodium-void reactivity measurement method for a sodium-cooled fast reactor. The method comprises the following steps: (I), a measurement position is selected in a reactor core; (II) a sodium coolant for fuel components of the reactor core exists in the measurement position in the step (I) in a normal operation state, the reactor is adjusted to a tiny super-critical state, the state parameter of the reactor core, the rod positions of all control rods and counting and reactivity data of a neutron detector are recorded, and the super-critical reactivity Rho1 of a reference point is calculated in a fitting manner; (III) shutdown is performed, the sodium-void experimental assembly without the sodium coolant replaces fuel components in the step (II) when the counting drops to the background, and the super-critical reactivity Rho2 of a measurement point is obtained by adopting the method of the step (II); (IV) the measured value of the sodium-void reactivity is equal to (Rho1-Rho2); and (V) the measured value is subject to various modifications. The invention also provides a sodium-void experimental assembly used in the method. By adopting the method and the assembly which are provided by the invention, more accurate sodium-void reactivity value can be obtained.

Description

technical field [0001] The invention belongs to the technical field of reactor reactivity system calibration, and in particular relates to a method for measuring the sodium cavitation reactivity of a sodium-cooled fast reactor and a sodium cavitation experimental component. Background technique [0002] Fast neutron reactor is the main reactor type of next-generation nuclear energy system, among which sodium-cooled fast neutron power reactor (referred to as sodium-cooled fast reactor) occupies an important position in the development of next-generation nuclear energy system due to its technical maturity and excellent performance. . Sodium-cooled fast reactor uses liquid metal sodium as coolant, and its sodium cavitation reactivity effect is one of the important contents in the design process, involving fuel selection, core layout, safety system and fuel management, safety analysis, etc. The China Experimental Fast Reactor is the first sodium-cooled fast neutron power reacto...

Claims

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Application Information

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IPC IPC(8): G21C17/025G21C3/16
CPCY02E30/40Y02E30/30
Inventor 喻宏周科源胡赟杨晓燕刚直陈仪煜
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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