Thermalhydraulic evaluations for a canflex bundle with natural or recycled uranium fuel in the uncrept and crept channels of a candu-6 reactor /

समान संसाधन

• Comparison of dryout power data between canflex MK-V and canflex MK-IV bundle strings in uncrept and crept channels /
  द्वारा: Jun, Ji Su.
• Predictions of critical heat flux using the ASSERT-PV subchannel code for a CANFLEX variant bundle /
  द्वारा: Onder, Ebru Nihan.
• Extendible and stably extendible vector bundles over real projective spaces /
  द्वारा: Kobayashi, Teiichi.
• A study on lexical bundles in english and vietnamese scientific writing
  द्वारा: Tạ Thị Trâm Anh
  प्रकाशित: (2025)
• Lectures on vector bundles over Riemann surfaces/
  द्वारा: Gunning, R. C. 1931-
  प्रकाशित: (1967)