VIPRE-01: A thermal-hydraulic code for reactor cores

Technical Report · Tue Aug 01 04:00:00 EDT 1989

OSTI ID:5740653

Cuta, J M; Koontz, A S; Stewart, C W; Montgomery, S D; Nomura, K K ^[1]

---

1. Pacific Northwest Lab., Richland, WA (USA)

The VIPRE-01 thermal hydraulics code for PWR and BWR analysis has undergone significant modifications and error correction. This manual for the updated code, designated as VIPRE-01 Mod-02, describes improvements that eliminate problems of slow convergence with the drift flux model in transient simulation. To update the VIPRE-01 code and its documentation the drift flux model of two-phase flow was implemented and error corrections developed during VIPRE-01 application were included. The project team modified the existing VIPRE-01 equations into drift flux model equations by developing additional terms. They also developed and implemented corrections for the errors identified during the last four years. They then validated the modified code against standard test data using selected test cases. The project team prepared documentation revisions reflecting code improvements and corrections to replace the corresponding sections in the original VIPRE documents. The revised VIPRE code, designated VIPRE-01 Mod-02, incorporates improvements that eliminate many shortcomings of the previous version. During the validation, the code produced satisfactory output compared with test data. The revised documentation is in the form of binder pages to replace existing pages in three of the original manuals.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA); Pacific Northwest Lab., Richland, WA (USA)
• Sponsoring Organization: EPRI
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5740653
• Report Number(s): EPRI-NP-2511-CCM-A-Vol.2-Rev.3
• Country of Publication: United States
• Language: English

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)
BWR TYPE REACTORS
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
MODIFICATIONS
OPERATION
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS