Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (5): 50601-050601.doi: 10.11889/j.0253-3219.2020.hjs.43.050601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Unprotected loss of flow condition analysis of sodium cold fast reactor based on lumped parameter method

Peng FANG1,2,Yongwei YANG1,2(),Zelong ZHAO1,2   

  1. 1.Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
    2.School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2019-12-02 Revised:2020-01-21 Online:2020-05-15 Published:2020-05-07
  • Contact: Yongwei YANG E-mail:yangyongwei@impcas.ac.cn
  • About author:FANG Peng, male, born in 1993, graduated from Shandong University of Science and Technology in 2017, master student, major in nuclear energy science and engineering
  • Supported by:
    Strategic Priority Research Program of Chinese Academy of Sciences(XDA21010202)

Abstract: Background

Fast reactor is an ideal advanced reactor with high fuel efficiency and transmutable nuclear waste. The pool loop layout is widely adopted for the fast reactor, therefore, the safety analysis of pool-type fast reactor has important practical significance.

Purpose

This study aims to analyze the safety of the pool-type fast reactor in unprotected flow loss condition by using lumped parameter method.

Methods

First fo all, the lumped parameter model of the primary path of pool-type sodium cooled fast reactor was established. Then, based on MATLAB platform, the nuclear thermal coupling program was written to analyse the safety of unprotected flow loss conditions. Finally, the calculated results were compared with the experimental results and the calculation results of other institutions.

Results

The results of the program are in good agreement with other compared results, which verifies the reliability of the program.

Conclusions

The method can provide a preliminary estimate of the core behavior and inherent safety of pool-type sodium cooled fast reactor in an unprotected flow loss accident.

Key words: Lumped parameter method, Pool-type sodium cooled fast reactor, Analysis of unprotected flow loss condition

CLC Number: 

  • TL364+.4