Calculations of maximum temperature in centerline of nuclear fuel rod and fissile fuel enrichment in hybrid reactor

Ipek O., Yapici H., Ozceyhan V.

ARABIAN JOURNAL FOR SCIENCE AND ENGINEERING, vol.29, pp.43-65, 2004 (SCI-Expanded) identifier identifier

  • Publication Type: Article / Article
  • Volume: 29
  • Publication Date: 2004
  • Journal Name: ARABIAN JOURNAL FOR SCIENCE AND ENGINEERING
  • Journal Indexes: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Page Numbers: pp.43-65
  • Süleyman Demirel University Affiliated: No

Abstract

Behavior of nuclear fuel material and temperature distribution in fuel rods are observed over 4 years for a discrete time interval of Deltat = 15 days, different coolants, and volumetric ratio epsilon (epsilon = V-m/V-f) by a plant factor (PF) of 75% under various first wall loads (P. = 2, 5, 7, 8, 9, and 10 MWm(-2)). The fissile fuel zone in a hybrid reactor fueled with UO2 is considered to be cooled with four different coolants, gas (He, CO2) flibe (Li2BeF4), natural lithium (Li), and eutectic lithium (Li17Pb83). Plasma chamber dimension, DR, with a line fusion neutron source is 300 cm in hybrid system.