RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation. [PWR and BWR]
This portion of the RELAP4/MOD5 User's Manual presents the details of setting up and entering the reactor model to be evaluated. The input card format and arrangement is presented in depth, including not only cards for data but also those for editing and restarting. Problem initalization including pressure distribution and energy balance is discussed. A section entitled ''User Guidelines'' is included to provide modeling recommendations, analysis and verification techniques, and computational difficulty resolution. The section is concluded with a discussion of the computer output form and format.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- DOE Contract Number:
- E(10-1)-1375
- OSTI ID:
- 7349742
- Report Number(s):
- ANCR-NUREG-1335(Vol.2); TRN: 76-022891
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation. [BWR; PWR]
RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Supplement 1, RELAP4/MOD5, Update 2. [BWR; PWR]
RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume I. RELAP4/MOD5 description. [BWR; PWR]
Technical Report
·
Tue Jun 01 00:00:00 EDT 1976
·
OSTI ID:7349742
RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Supplement 1, RELAP4/MOD5, Update 2. [BWR; PWR]
Technical Report
·
Sun Aug 01 00:00:00 EDT 1976
·
OSTI ID:7349742
RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume I. RELAP4/MOD5 description. [BWR; PWR]
Technical Report
·
Tue Jun 01 00:00:00 EDT 1976
·
OSTI ID:7349742
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
REACTOR SAFETY
COMPUTER CODES
R CODES
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
FORTRAN
MANUALS
MATHEMATICAL MODELS
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
TEMPERATURE GRADIENTS
TIME DEPENDENCE
ACCIDENTS
COOLING SYSTEMS
DOCUMENT TYPES
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
PROGRAMMING LANGUAGES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
REACTOR SAFETY
COMPUTER CODES
R CODES
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
FORTRAN
MANUALS
MATHEMATICAL MODELS
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
TEMPERATURE GRADIENTS
TIME DEPENDENCE
ACCIDENTS
COOLING SYSTEMS
DOCUMENT TYPES
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
PROGRAMMING LANGUAGES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled