Method of synthesizing reactor core power distribution for reactor core protection system based on in-core instrument signal using ordinary kriging method
AssigneeKepco Nuclear Fuel Co., Ltd.
InventorsYoung Min Kwon, Byung Chan Baek, Dong-su Kim, Wook Lee, Do-young Oh
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Abstract
A method of synthesizing reactor core power distribution is disclosed. According to the method, the power of all fuel assemblies in a reactor core is calculated from powers of fuel assemblies in which in-core instruments are located using the ordinary kriging methodology. Also, a hot-pin power distribution of each fuel assembly is synthesized from the power of all fuel assemblies calculated, whereby more accurate hot-pin axial power distribution, rather than pseudo hot-pin axial power distribution, may be synthesized.
Claims4
A method of synthesizing reactor core power distribution for a reactor core protection system based on an in-core instrument signal using an ordinary kriging method, the method comprising steps of:
- (a) calculating a power of all fuel assemblies in a reactor core from powers of fuel assemblies in which in-core instruments are located using the ordinary kriging method;
- (b) obtaining axial power distribution of a node for each fuel assembly by artificial neural network synthesis of axial power distribution based on results of step (a);
- and
- (c) obtaining hot-pin power distribution of the node for each fuel assembly by multiplying the axial power distribution of the node obtained in step (b) by a 1-pin correlation factor obtained from a reactor core design code and a ratio of the powers of the fuel assemblies to an average power of an entire reactor core,
- wherein in step (c), the hot-pin power distribution of the node is calculated by multiplying the axial power distribution of the node by the ratio of a power of the fuel assembly to the average power of the entire reactor core and the 1-pin correlation factor corresponding to the node, as in the following equation,
- PD
- jl
- =
- FZ
- jl
- ×
- ∑
- k
- =
- 1
- 5
-
- P
- jk
- P
- AVG
- ×
- [
- (
- 1
- -
- pin
- )
- /
- RPF
- ]
- jl
- ,
- [
- Equation
- ]
- wherein PDjl is the hot-pin power of an lth node of a jth fuel assembly, FZjl is the axial power distribution of the lth node of the jth fuel assembly, Pjk is a calculated power of a kth level of the jth fuel assembly, PAVG is the average power of the entire reactor core, and [(1−Pin)/RPF]jl is the 1-pin correlation factor corresponding to the lth node of the jth fuel assembly.
Dependencies are inferred from the claim text.