Nuclear Techniques ›› 2015, Vol. 38 ›› Issue (3): 30603-030603.doi: 10.11889/j.0253-3219.2015.hjs.38.030603

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Production and release of 14C in TMSR-SF1

ZHU Xingwang WANG Shuai PENG Chao HE Zhaozhong CHEN Kun   

  1. (Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China)
  • Received:2014-10-08 Revised:2014-11-07 Online:2015-03-10 Published:2015-03-09

Abstract: Background: As one of the six candidates recommended by the fourth generation reactor forum, Molten Salt Reactor (MSR) owns many features such as high outlet temperature, high energy density, and anhydrous cooling. In the core of the first Thorium Molten Salt Reactor with Solid Fuel (TMSR-SF1), most of the structure materials are graphite. 13C in graphite and the impurities N and O in coolant can be activated to produce 14C. 14C has long half-life, it can be involved in various complex biological cycle with other stable nuclides 12C and 13C. In TMSR-SF1, 14C is widely distributed in the coolant, the active core and the structure materials. Purpose: The aim is to study the production and release of 14C in TMSR-SF1. Methods: According to the design parameters of TMSR-SF1, TRITON (Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion) of SCALE6.1 (Standardized Computer Analyses for Licensing Evaluation) was applied for the transport burnup coupled calculation. Results: Computational results show that the radioactivity of 14C in main loop mainly comes from the activation of N, and the total amount of radioactivity of 14C in the main loop is 0.34 TBq each year. Conclusion: TMSR-SF1 could meet the current emissions standards of 14C according to current design parameters.

Key words: Thorium Molten Salt Reactor with Solid Fuel (TMSR-SF1), 14C, Production, Release