Analyses of fluid flow and heat transfer inside calandria vessel of candu-6 reactor using CFD /

समान संसाधन

• Development of best practice guidelines for CFD in nuclear reactor safety /
  द्वारा: Mahaffy, J.
• CFD application to the regulatory assessment of fac-caused CANDU feeder pipe wall thinning issue /
  द्वारा: Kang, Dong-Gu.
• Assessment of CFD codes used in nuclear reactor safety simulations /
  द्वारा: Smith, B.L..
• A review of CANDU feeder wall thinning /
  द्वारा: Chung, H.-S.
• Extension of CFD codes application to two-phase flow safety problems /
  द्वारा: Bestion, D.