Nuclear plant analyzer development at INEL. [PWR; BWR]
Conference
·
OSTI ID:5624620
The Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC) has sponsored development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes the status of the NPA project at the INEL after one year of development. When completed, the NPA will be an integrated network of analytical tools for performing reactor plant analyses. Development of the NPA in FY-1983 progressed along two parallel pathways; namely, conceptual planning and software development. Regarding NPA planning, and extensive effort was conducted to define the function requirements of the NPA, conceptual design, and hardware needs. Regarding software development conducted in FY-1983, all development was aimed toward demonstrating the basic concept and feasibility of the NPA. Nearly all software was developed and resides on the INEL twin Control Data Corporation 176 mainframe computers.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5624620
- Report Number(s):
- EGG-M-21283; CONF-8310143-41; ON: DE84002209
- Country of Publication:
- United States
- Language:
- English
Similar Records
Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory. [PWR; BWR]
Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory
Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6376652
Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:6277993
Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory
Conference
·
Wed Oct 01 00:00:00 EDT 1986
·
OSTI ID:5961417
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ANALOG SYSTEMS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
FUNCTIONAL MODELS
OPERATION
PWR TYPE REACTORS
REACTOR OPERATION
REACTOR SAFETY
REACTOR SIMULATORS
REACTORS
SAFETY
SIMULATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ANALOG SYSTEMS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
FUNCTIONAL MODELS
OPERATION
PWR TYPE REACTORS
REACTOR OPERATION
REACTOR SAFETY
REACTOR SIMULATORS
REACTORS
SAFETY
SIMULATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS