Development and preliminary validation of a steam generator 3D thermohydraulics analysis code STAF
- 1. Department of Engineering Physics, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, WI 53706 (United States)
- 2. School of Nuclear Science and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049 (China)
Description
Highlights: • A steam generator thermohydraulics analysis code STAF is developed based on FLUENT. • Heat transfer from primary to secondary side is calculated during iteration in STAF. • Localized flow characteristics in steam generator can be obtained by STAF. • STAF is validated by simulating the AP 1000 steam generator. • STAF is validated by FRIGG test. - Abstract: Porous media model in Fluent code, coupled with two-phase mixture flow model, resistance model of tubes and heat transfer model through tubes, is employed to develop a steam generator thermohydraulics analysis code STAF (Steam generator Thermohydraulics Analysis code based on Fluent). In this code, the heat transfer from primary to secondary side is calculated three-dimensionally during iteration. The localized velocity, temperature, enthalpy, quality and void fraction in steam generator can be obtained by this code. STAF is validated in two ways. First, STAF is used to calculate the thermal-hydraulic parameters in steam generator of AP 1000. The calculated results are compared with designed values to prove that the coupled heat transfer calculation in STAF is accurate. Second, STAF is employed to simulate the FRIGG test to validate the localized parameter calculation performance by comparing the calculated localized void fraction with test values.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2015.12.027Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2015.12.027;
- PII
- S0029-5493(15)00613-5;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 298
- Journal Page Range
- p. 135-148
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48005600
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; ENTHALPY; FLOW MODELS; HEAT; HEAT TRANSFER; MIXTURES; POROUS MATERIALS; PWR TYPE REACTORS; S CODES; STEAM; STEAM GENERATORS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TUBES; VALIDATION; VOID FRACTION; VOIDS
- Descriptors DEC
- BOILERS; COMPUTER CODES; DISPERSIONS; ENERGY; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; FLUID MECHANICS; HYDRAULICS; MATERIALS; MATHEMATICAL MODELS; MECHANICS; PHYSICAL PROPERTIES; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.