Transient Analysis of Fluoride-salt-cooled High-temperature Reactor Test Facility Based on Modified RELAP5/MOD3.2

XU Rong-shuan; LIU Li-min; WANG Ning; ZHANG Da-lin; WANG Cheng-long; QIU Sui-zheng; SU Guang-hui

doi:10.7538/yzk.2017.51.05.0828

Atomic Energy Science and Technology > 2017 > 51(5): 828-835. > DOI: 10.7538/yzk.2017.51.05.0828

XU Rong-shuan, LIU Li-min, WANG Ning, ZHANG Da-lin, WANG Cheng-long, QIU Sui-zheng, SU Guang-hui. Transient Analysis of Fluoride-salt-cooled High-temperature Reactor Test Facility Based on Modified RELAP5/MOD3.2[J]. Atomic Energy Science and Technology, 2017, 51(5): 828-835. DOI: 10.7538/yzk.2017.51.05.0828

Citation:

PDF (5934 KB)

Transient Analysis of Fluoride-salt-cooled High-temperature Reactor Test Facility Based on Modified RELAP5/MOD3.2

1.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
2.
Nuclear Power Institute of China, Chengdu 610213, China

More Information

Graphical Abstract

Abstract

Abstract

The compact integral effects test (CIET) facility was designed to investigate the thermal hydraulic responses of fluoride-salt-cooled high-temperature reactor. CIET facility uses DOWTHERM A fluid to simulate fluoride salt. Thermo-physical properties and transport of DOWTHERM A were implemented into the RELAP5/MOD3.2. The modified RELAP5 code was adopted to study thermal hydraulic behavior of DOWTHERM A under forced circulation operation and natural circulation operation of CIET facility respective-ely. Calculation results of core inlet and outlet temperatures and the coiled tube air heater outlet temperature are in good agreement with the corresponding experimental data under forced circulation operation. The inlet temperatures of coiled tube air heater are slightly different from the experiment data. In natural circulation the computational results indicate that the decay heat is mainly removed through the DRACS. The computational flow rates of DHX and DRACS are close to the experiment data. Furthermore, the relative error of flow rate between calculation results and experiment data is about 10%. The results prove the accuracy of the modified RELAP5/MOD3.2.
- fluoride-salt-cooled high-temperature reactor,
- compact integral effects test,
- RELAP5/MOD3.2

FullText(HTML)

References (14)

References

[1]	INGERSOLL D T, FORSBERG C W. Overview and status of the advanced high-temperature reactor[C]∥Proceedings of the International Congress on Advanced Nuclear Power Plants. Reno, Nevada: [s. n.], 2006.
[2]	苏光辉. 核动力系统热工水力计算方法[M]. 北京：清华大学出版社，2013.
[3]	WANG C, ZHANG D, QIU S, et al. Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor[J]. Nuclear Engineering and Design, 2013, 265: 691-700.
[4]	ZWEIBAUM N, SCARLAT R O, PETERSON P F. Verification and validation of a single-phase natural circulation loop model in RELAP5-3D[C]∥2013 RELAP5 International Users Group Seminar. Idaho, USA: [s. n.], 2013.
[5]	ZWEIBAUM N, BICKEL J E, GUO Z, et al. Design, fabrication and startup testing in the compact integral effects test facility in support of fluoride-salt-cooled high-temperature reactor technology[C]∥NURETH-16. USA: American Nuclear Society, 2015.
[6]	BICKEL J E, GUBSER A J, GUO Z, et al. Design, fabrication and startup testing in the compact integral effects test (CIET 1.0) facility in support of fluoride-salt-cooled high-temperature reactor technology[R]. USA: Department of Nuclear Engineering, 2014.
[7]	ZWEIBAUM N. Experimental validation of passive safety system models: Application to design and optimization of fluoride-salt-cooled high-temperature reactors[D]. Berkeley, USA: University of California, 2015.
[8]	ZWEIBAUM N, SCARLAT R O, PETERSON P F. Design of a compact integral effects test facility for fluoride-salt-cooled high-temperature reactors[C]∥Proceedings of the American Nuclear Society 2013 Winter Conference. Washington D. C.: American Nuclear Society, 2013.
[9]	GROUP T H. Temperature-dependent thermophysical properties for fluoride salts and simulant fluids[R]. Berkeley, USA: University of California, 2013.
[10]	ZEMANSKY M W, DITTMAN R H, SCOTT H L. Heat and thermodynamics[J]. American Journal of Physics, 1998, 66(2): 164-167.
[11]	CARLSON K E, RIEMKE R A, ROUHANI S Z, et al. RELAP5/MOD3 code manual volume Ⅰ: Code structure, system models and solution methods, NUREG/CR-5535[R]. Washington D. C.: US NRC, 1990.
[12]	LIU L, YAN Q, ZHANG D, et al. Investigation of the modified RELAP5/MOD3.2 capability to simulate the transients of the fluoride-salt high-temperature reactors[C]∥ICONE24. USA: American Society of Mechanical Engineers, 2016.
[13]	DITTUS F, BOELTER L. Heat transfer in automobile radiators of the tubular type[J]. International Communications in Heat and Mass Transfer, 1985, 12(1): 3-22.
[14]	SIEDER E N, TATE G E. Heat transfer and pressure drop of liquids in tubes[J]. Industrial & Engineering Chemistry, 1936, 28(12): 1429-1435.

Cited By

Get Citation

PDF

XML

Article views (362) PDF downloads (1250)

Turn off MathJax

Article Contents

Abstract

References

Transient Analysis of Fluoride-salt-cooled High-temperature Reactor Test Facility Based on Modified RELAP5/MOD3.2

Abstract

References

Catalog

Export File

Citation

Format

Content