THERMAL STRESSES OF TRANSIENT PARTS OF THE REACTOR OUTLET TUBING IN THE CASE OF THERMAL SHOCKS.

Journal Article · Wed Jan 01 00:00:00 EST 1969 · Jad. Energ., 15: 15-21(Jan. 1969).

OSTI ID:4831439

Kunes, J; Svigler, V; Vavroch, O

• Research Organization: Technical Univ., Plzen, Czech.
• NSA Number: NSA-23-013516
• OSTI ID: 4831439
• Journal Information: Jad. Energ., 15: 15-21(Jan. 1969)., Other Information: Orig. Receipt Date: 31-DEC-69
• Country of Publication: Country unknown/Code not available
• Language: Czech

Related Subjects

N38160* -Power Reactor Development-Auxiliary & Emergency Systems
ANALYSIS
COOLANT LOOPS
FLUID FLOW
GAS COOLANT
HEAT TRANSFER
PIPES
REACTORS
STRESSES
TEMPERATURE
PIPES/stresses in gas-cooled reactor gas-outlet
analysis of thermoelastic
(E/T)
REACTORS
GAS-COOLED/pipes for
analysis of temperature gradients and thermoelastic stresses in gas-outlet
(E/T)
PIPES/ temperature distribution in gas-cooled reactor gas-outlet
analysis of gradients in
(E/T)