HYDNA-DIGITAL COMPUTER PROGRAM FOR HYDRODYNAMIC TRANSIENTS IN A PRESSURE TUBE REACTOR OR A CLOSED CHANNEL CORE

Technical Report · Wed Feb 01 04:00:00 EST 1961

OSTI ID:4004757

Currin, H B; Hunin, C M; Rivlin, L; Tong, L S

A transient thermal-hydraulic code, HYDNA, was pro grammed for the IBM- 704 digital computer to calculate the coolant density distribution, to determine the DNB (burnout) point, and to detect the flow instability in a pressure-tube or closed-channel reactor core. The nuclear kinetic equation was not included in the code, but the nuclear transient can be incorporated with the thermal- hydraulic transient by conducting an iterative calculation of coolant density and power density with this code and a nuclear code. (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-15-019510
• OSTI ID: 4004757
• Report Number(s): CVNA-77
• Country of Publication: United States
• Language: English

Related Subjects

BURNOUT
COMPUTERS
COOLANT LOOPS
COOLANTS
DENSITY
DEPARTURE NUCLEATE BOILING
DETECTION
DIGITAL SYSTEMS
DISTRIBUTION
ELEMENTARY PARTICLES
ENGINEERING AND EQUIPMENT
FIELD THEORY
FLUID FLOW
HEAT TRANSFER
HYDRA
HYDRAULICS
IBM 704
INTERACTIONS
MATHEMATICS
NUCLEATE BOILING
POWER
PROGRAMMING
QUANTITATIVE ANALYSIS
REACTIVITY
REACTOR CORE
REACTORS
STABILITY
THERMODYNAMICS
TRANSIENTS