The accelerator-driven subcritical reactor system (ADS) is a kind of nuclear reactor which can burn minor actinide waste products produced from conventional reactors with inherent safety features. In this paper, the thermal-hydraulic model and a corresponding program for a 10 MW helium-cooled experimental ADS are presented. Through the analysis of the heat transfer mechanism in ADS, the thermal-hydraulic model of ADS was built, in which the solid domain is simulated with three-dimensional heat conduction model and the fluid domain is simulated with the one-dimensional quasi-static model. In order to analyze the transient characteristics of ADS with cooling system, a RELAP5–TRCAP coupling model for the cooling system was established, in which the decay heat of the target and core is considered. The results of steady condition and transients demonstrate the effectiveness of the transient model.
Skip Nav Destination
Article navigation
April 2017
Technical Briefs
Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System
Tianji Peng,
Tianji Peng
Institute of Modern Physics,
Chinese Academy of Sciences,
Lanzhou 730000, China
e-mail: pengtianji@163.com
Chinese Academy of Sciences,
Lanzhou 730000, China
e-mail: pengtianji@163.com
Search for other works by this author on:
Zhiwei Zhou
Zhiwei Zhou
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
Tsinghua University,
Beijing 100084, China
Search for other works by this author on:
Tianji Peng
Institute of Modern Physics,
Chinese Academy of Sciences,
Lanzhou 730000, China
e-mail: pengtianji@163.com
Chinese Academy of Sciences,
Lanzhou 730000, China
e-mail: pengtianji@163.com
Zhiwei Zhou
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
Tsinghua University,
Beijing 100084, China
1Corresponding author.
Manuscript received April 14, 2016; final manuscript received October 18, 2016; published online March 1, 2017. Assoc. Editor: Yanping Huang.
ASME J of Nuclear Rad Sci. Apr 2017, 3(2): 024502 (6 pages)
Published Online: March 1, 2017
Article history
Received:
April 14, 2016
Revised:
October 18, 2016
Citation
Peng, T., and Zhou, Z. (March 1, 2017). "Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System." ASME. ASME J of Nuclear Rad Sci. April 2017; 3(2): 024502. https://doi.org/10.1115/1.4035333
Download citation file:
57
Views
Get Email Alerts
Cited By
Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
ASME J of Nuclear Rad Sci (October 2023)
Main Parameters Influencing the Level of Labile Contamination and the Removal Factor
ASME J of Nuclear Rad Sci (October 2023)
Handbook of Generation IV Nuclear Reactors Edition 2
ASME J of Nuclear Rad Sci (July 2023)
Related Articles
Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System
J. Eng. Gas Turbines Power (February,2011)
Development of SNTA Code System for SCWR Core Steady-State Analysis
ASME J of Nuclear Rad Sci (April,2017)
A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor
ASME J of Nuclear Rad Sci (January,2017)
Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations
ASME J of Nuclear Rad Sci (April,2018)
Related Chapters
Introduction
Thermal Management of Microelectronic Equipment
The Special Characteristics of Closed-Cycle Gas Turbines
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Control and Operational Performance
Closed-Cycle Gas Turbines: Operating Experience and Future Potential