Nuclear Techniques ›› 2019, Vol. 42 ›› Issue (6): 60602-060602.doi: 10.11889/j.0253-3219.2019.hjs.42.060602

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Calculation and analysis of activated corrosion products of multi-phase in water cooling loops under fusion reactor

Qingyang GUO,Jingyu ZHANG(),Yixue CHEN   

  1. School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
  • Received:2019-02-23 Revised:2019-04-22 Online:2019-06-10 Published:2019-06-18
  • Contact: Jingyu ZHANG E-mail:poptnt@163.com
  • About author:GUO Qingyang, female, born in 1991, graduated from Southwest University of Science and Technology in 2015, doctoral student, focusing on the analysis of radioactive source term in reactor
  • Supported by:
    Supported by National Natural Science Foundation of China (No.11605058), the Fundamental Research Funds for the Central Universities(No.2019QN093)

Abstract: Background

In the water-cooled loops of fusion reactor, corrosion products are produced in the process of interaction between the structure materials and the coolant. When coolant flows in the flux region, the corrosion products will be activated by neutrons to produce activated corrosion products (ACPs). The radiation field generated by the ACPs has the greatest impact on the occupational radiation exposure (ORE) of personnel in the process of maintenance and overhaul.

Purpose

This study aims to accurately analyze the source terms of ACPs in water-cooled loops of fusion reactor, and perform some simulation calculation of ACPs.

Methods

Firstly a four-phase three-node model for calculating radioactivity of ACPs was proposed, in which the main behaviors of ions, particles, deposits layer and oxide layer were considered, and the code CATE V3.0 was developed based on CATE V2.1. Then the composition and radioactivity of ACPs in the divertor cooling loop of International Thermonuclear Experimental Reactor (ITER) were calculated with CATE V3.0. Finally the dose rate at shutdown after normally operation for 1.2 a was calculated with the point kernel code ARShield. [Results &

Conclusions

The oxide layer is the main contributor to radioactivity in the flux region whilst deposits layer is the main contributor in the out-flux region. The short-lived nuclides such as 64Cu and 60Com, are the main contributors of radioactivity during the operation of reactor, but long-lived nuclides such as 58Co and 60Co, are the main contributors to the dose rate due to the decay of the short-lived nuclides after shutdown of reactor.Key words Activated corrosion products, Four-phase three-node model, ITER, CATE V3.0, Dose rate

CLC Number: 

  • TL929