A Study of Neutronics Effects of the Spacer Grids in a Typical PWR via Monte Carlo Calculation

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Spacer grids play an important role in maintaining the proper form of the fuel assembly structure and ensuring the safety of reactor core design. This study applies the Monte Carlo method to the analysis of the neutronics effects of spacer grids in a typical pressurized water reactor (PWR). The core problem used to analyze the neutronics effects of spacer grids is a modified version of Korea Advanced Institute of Science and Technology benchmark problem 1B, based on an Advanced Power Reactor 1400 (APR1400) core model. The spacer grids are modeled and added to this test problem in various ways. Then, by running MCNP5 for all cases of spacer grid modeling, some important numerical results, such as the effective multiplication factor, the spatial distributions of neutron flux, and its energy spectrum are obtained. The numerical results of each case of spacer grid modeling are analyzed and compared to assess which type has more advantages in accuracy of numerical results and effectiveness in terms of geometry building. The conclusion is that the most realistic modeling for Monte Carlo calculation is the "volume-preserving " streamlined heterogeneous spacer grids, but the "banded " dissolution spacer grids modeling is a more practical yet accurate model for routine (deterministic) analysis.
Publisher
KOREAN NUCLEAR SOC
Issue Date
2016-02
Language
English
Article Type
Article
Citation

NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.1, pp.33 - 42

ISSN
1738-5733
DOI
10.1016/j.net.2015.10.001
URI
http://hdl.handle.net/10203/207986
Appears in Collection
NE-Journal Papers(저널논문)
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