VIPRE-01: A thermal-hydraulic code for reactor cores
Creators
- 1. Pacific Northwest Lab., Richland, WA (USA)
Description
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
Availability note (English)
Available from Research Reports Center, Box 50490, Palo Alto, CA 94303.Additional details
Additional titles
- Subtitle (English)
- Volume 2, User's manual: Revision 3
Publishing Information
- Imprint Pagination
- 38 p.
- Report number
- EPRI-NP--2511-CCM-A-Vol.2-Rev.3
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21014128
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature, Computer Program Description
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER PROGRAM DOCUMENTATION; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; MODIFICATIONS; PWR TYPE REACTORS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; TRANSIENTS; V CODES
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC06-76RL01830