Extension and validation of RELAP/SCDAPSIM/MOD4.0 code on FHR

被引：0

作者：

Jiang S. ^{[1
,2
]}

Cheng M. ^{[1
]}

Dai Z. ^{[1
]}

Chen Y. ^{[1
]}

机构：

[1] Shanghai Institute of Applied Physics, Chinese Academy of Science, Shanghai

[2] University of Chinese Academy of Sciences, Beijing

来源：

| 1600年 / Atomic Energy Press卷 / 37期

关键词：

Code validation; FHR; FLiNaK test loop; RELAP/SCDAPSIM/MOD4.0;

D O I：

10.13832/j.jnpe.2016.06.0033

中图分类号：

学科分类号：

摘要：

On the basis of RELAP/SCDAPSIM/MOD4.0 code, adding and implementing the thermophysical properties and heat transfer coefficients of FLiNaK into the source code, the RELAP5-FHR code is developed, which is suitable for the analyzing of the FHR system. Then the RELAP5-FHR code is validated by the experimental data of the FLiNaK high temperature molten salt test loop. The results indicate that the simulation results from the RELAP5-FHR code are in close agreement with the experimental data, which validates the applicability of RELAP5-FHR code for FHR. © 2016, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：33 / 36

页数：3

共 6 条

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[2] RELAP5/MOD4.0 Code Manual Volume 1: Code Structure, System Models, and Solution Methods
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[4] Cantor S.J.W., Cooke A.S., Dworkin G.D., Et al., Physical Properties of Molten-Salt Reactor Fuel, Coolant, and Flush Salt, (1968)
[5] Powers W.D., Cohen S.I., Greene N.D., Physical Properties of Molten Reactor Fuels and Coolants, Nuclear Science and Engineering, 17, pp. 200-211, (1963)
[6] Gnielinski V., New equations for heat and mass transfer in turbulent pipe and channel flow, (2005)

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