Science and Technology of Nuclear Installations (Jan 2014)

Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor

  • Fan Zhang,
  • Dao-gang Lu,
  • Dan-ting Sui,
  • Bo Yuan,
  • Chao Guo

DOI
https://doi.org/10.1155/2014/279092
Journal volume & issue
Vol. 2014

Abstract

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SCWR (Supercritical Water Reactor) is one of the promising Generation IV nuclear systems, which has higher thermal power efficiency than current pressurized water reactor. It is necessary to perform the thermal equilibrium and thermal power calculation for the conceptual design and further monitoring and calibration of the SCWR. One visual software named H-Power was developed to calculate thermal power and its uncertainty of SCWR, in which the advanced IAPWS-IF97 industrial formulation was used to calculate the thermodynamic properties of water and steam. The ISO-5167-4: 2003 standard was incorporated in the code as the basis of orifice plate to compute the flow rate. New heat balance model and uncertainty estimate have also been included in the code. In order to validate H-Power, an assessment was carried out by using data published by US and Qinshan Phase II. The results showed that H-Power was able to estimate the thermal power of SCWR.