The application of steam generator code CCM based on theoretical drift-flux
Creators
- 1. Tsinghua Univ., Beijing (China). Inst. of Nuclear and New Energy Technology
- 2. Bernaysstr. Munich (Germany)
Description
A coolant channel module (CCM) is presented to simulate, in a very general way, the thermal-hydraulic behavior of single-and two-phase flow along a heated (or cooled) vertical, inclined or horizontal coolant channel. It is based on a drift-flux model with governing equations describing mass, momentum and energy balances for both the steady-state and transient flows in such a general channel. A special time-dependent quadratic polygon approximation method using a modified finite volume algorithm is employed to establish a connection between nodal boundaries and nodal-mean parameters. By using the code CCM, the U-tube steam generator simulation program UTSG-3 has been assembled, which simulates the transient behavior when steam generator operates under either normal or accident conditions. The transient responses of operation parameters of a steam generator similar to that of Daya Bay NPP are studied by means of different operation parameter perturbations. The results show that the UTSG-3 is capable of simulating the dynamic behavior of U-tube steam generator. (authors)
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 26
- Journal Issue
- 3
- Journal Page Range
- p. 199-203
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 38093618
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- C CODES; DAYA BAY-1 REACTOR; FLOW MODELS; HEAT TRANSFER; SIMULATION; STEADY-STATE CONDITIONS; STEAM GENERATORS; THERMAL HYDRAULICS; TRANSIENTS; TWO-PHASE FLOW; U CODES; USES
- Descriptors DEC
- BOILERS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL MODELS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 figs., 2 refs.