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STEADY STATE THERMAL HYDRAULIC ANALYSIS OF A BOILING WATER REACTOR CORE, FOR VARIOUS OWER DISTRIBUTIONS, USING COMPUTER CODE THABNA. (INIS ; INIS-MF-3477)

STEADY STATE THERMAL HYDRAULIC ANALYSIS OF A BOILING WATER REACTOR CORE, FOR VARIOUS OWER DISTRIBUTIONS, USING COMPUTER CODE THABNA. (INIS ; INIS-MF-3477)
Paper図書
VENKAT RAJ, V.(et al.)International Atomic Energy Agency(International Atomic Energy Agency)1976.
Other Libraries in Japan
  • Author HeadingVENKAT RAJ, V.

FLATT - A COMPUTER PROGRAMME FOR CALCULATING FLOW AND TEMPERATURE TRANSIENTS IN NUCLEAR FUELS. (INIS ; INIS-MF-3475)

FLATT - A COMPUTER PROGRAMME FOR CALCULATING FLOW AND TEMPERATURE TRANSIENTS IN NUCLEAR FUELS. (INIS ; INIS-MF-3475)
Paper図書
VENKAT RAJ, V.(et al.)International Atomic Energy Agency(International Atomic Energy Agency)1976.
Other Libraries in Japan
  • Author HeadingVENKAT RAJ, V.

THERMAL HYDRAULIC ANALYSIS OF FUEL ROD CLUSTER FOR 100MWT. (INIS ; INIS-MF-1161)

THERMAL HYDRAULIC ANALYSIS OF FUEL ROD CLUSTER FOR 100MWT. (INIS ; INIS-MF-1161)
Paper図書
VENKAT RAJ, V.(et al.)International Atomic Energy Agency(International Atomic Energy Agency)1973.
Other Libraries in Japan
  • Author HeadingVENKAT RAJ, V.

Nuclear industry - challenges in chemical engineering (INIS ; INIS-MF-4166)

Nuclear industry - challenges in chemical engineering (INIS ; INIS-MF-4166)
Paper図書
Sen, S. [et al.]Bhabha Atomic Research Centre1978.1.
Other Libraries in Japan
  • Author Heading...adhukhan, H.K. Venkat Raj, V.

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