COUPLING OF RELAP5-SCDAP MOD4.0 AND NEUTRONIC CODES


Martinez-Quiroga V., Akbas S., 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

Abstract

High-fidelity and accurate nuclear system codes play a key role in the design and analysis of complex nuclear power plants, which consist of multiple subsystems, such as the reactor core (and its fuel, burnable poisons, control elements, etc.), the reactor internal structures, the vessel, and the energy conversion subsystem and beyond to grid demand. Most commonly the interplay between these various subsystems is modeled using coupled codes, each of which represents one of the subsystems. And the most common direct coupling is that of thermal hydraulics and neutronics codes.