PATHFINDER ATOMIC POWER PLANT. IBM-704 PROGRAM FOR REACTOR CONTAINMENT, PRESSURE SUPPRESSION ANALYSIS
A research and development program to investigate the feasibility of eliminating vapor closure for the Pathfinder Reactor was conducted. The major inquiry under the feasibility study involved an analysis of the complex transient conditions occurring in the reactor cavity, the pump rooms, and the entire reactor building following a primary system rupture. To solve the simultaneous nonlinear set of equations evolving from the heat, mass, and force balances in the system, an IBM-704 digital computer program was developed. The program has a very general input and can therefore be used with other containment designs. Input parameters include: initial pressures in reactor and throughout the containment building, hent capacity of vessel, decay heat, feedwater flow rate, enthalpy of feedwater, and volume of primary coolant system. (auth)
- Research Organization:
- Allis-Chalmers Mfg. Co. Atomic Energy Div., Milwaukee
- DOE Contract Number:
- AT(11-1)-589
- NSA Number:
- NSA-15-007075
- OSTI ID:
- 4120201
- Report Number(s):
- ACNP-6008
- Resource Relation:
- Other Information: For Northern States Power Co. and Central Utilities Atomic Power Associates. Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
Similar Records
PRESTO--A PRESSURIZER TRANSIENT PROGRAM FOR THE IBM-704
SPY (D1G), AN IBM-704 DIGITAL COMPUTER PROGRAM FOR THE CALCULATION OF NUCLEAR REACTOR THERMAL TRANSIENTS