RETRAN-02: A program for transient thermal-hydraulic analysis of complex fluid flow systems: Volume 1, Theory and numerics (Revision 4)
Technical Report
·
OSTI ID:6627455
RETRAN-02 represents a significant achievement in the development of a versatile and reliable computer program for use in best-estimate transient thermal-hydraulic analysis of light water reactor systems. The RETRAN-02 computer program is an extension of the RETRAN-01 program designed to provide analysis capabilities for (1) BWR and PWR transients, (2) small break loss of coolant accidents, (3) balance of plant modeling, and (4) anticipated transients without scram, while maintaining the analysis capabilities of the predecessor code. The RETRAN-02 computer code is constructed in a semimodular and dynamic dimensioned form where additions to the code can be easily carried out as new and improved models are developed. The NRC, at the request of a group of utilities, had Argonne National Laboratory perform a technical review of RETRAN-01 MOD003 and RETRAN-02 MOD002. This review was completed in May 1983, and the NRC issued a Safety Evaluation Report on RETRAN in September 1984. Revision 4 of the RETRAN-02 computer code manuals describes the MOD005 version of the code. This report (the first of a four-volume computer code manual) describes the theory and numerical algorithms of the RETRAN-02 code. The three companion volumes describe the programming details, the user input requirements and sample problem input and output files, and the verification and qualification performed with RETRAN. 186 refs., 75 figs., 30 tabs.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA); EI International, Inc., Idaho Falls, ID (USA)
- OSTI ID:
- 6627455
- Report Number(s):
- EPRI-NP-1850-CCM-A-Vol.1-Rev.4; ON: TI89004552
- Country of Publication:
- United States
- Language:
- English
Similar Records
RETRAN-02: a program for Transient Thermal-hydraulic Analysis of Complex Fluid Flow Systems. Volume 3. User's manual. Revision 2
RETRAN-02: a program for Transient Thermal-hydraulic Analysis of Complex Fluid Flow systems. Volume 2. Programmer's manual. Revision 2. [PWR; BWR]
RETRAN-02: a program for transient thermal-hydraulic analysis of complex fluid-flow systems. Volume 4. Applications. [PWR; BWR]
Technical Report
·
Mon Oct 01 00:00:00 EDT 1984
·
OSTI ID:6280290
RETRAN-02: a program for Transient Thermal-hydraulic Analysis of Complex Fluid Flow systems. Volume 2. Programmer's manual. Revision 2. [PWR; BWR]
Technical Report
·
Mon Oct 01 00:00:00 EDT 1984
·
OSTI ID:6219253
RETRAN-02: a program for transient thermal-hydraulic analysis of complex fluid-flow systems. Volume 4. Applications. [PWR; BWR]
Technical Report
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6391369
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
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
ALGORITHMS
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL LOGIC
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL POWER PLANTS
TRANSIENTS
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
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
ALGORITHMS
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL LOGIC
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL POWER PLANTS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS