SURVEY OF COUPLING SCHEMES IN TRADITIONAL COUPLED NEUTRONICS AND THERMAL-HYDRAULICS CODES

Akbas S., Martinez-Quiroga V., Aydogan F., Ougouag A. M., Allison C.

ASME International Mechanical Engineering Congress and Exposition (IMECE2015), Texas, United States Of America, 13 - 19 November 2015 identifier

  • Publication Type: Conference Paper / Full Text
  • Volume:
  • City: Texas
  • Country: United States Of America
  • Yozgat Bozok University Affiliated: No

Abstract

The design and the analysis of nuclear power plants (NPPs) require computational codes to predict the behavior of the NPP nuclear components and other systems (i.e., reactor core, primary coolant system, emergency core cooling system, etc.). Coupled calculations are essential to the conduct of deterministic safety assessments.