Simultaneous bottom and top-down rewetting calculations with the CATHARE code
Description
A top-down reflooding model was developed and implemented into the French best-estimate thermal-hydraulic code CATHARE2 V1.3E. A two-dimensional mesh moving along the wall with the quench front is used to resolve the heat conduction equation in the wall near the quench front. The results of the model validation and the first assessment calculations are given. The Winfrith single-tube top-down reflooding experiments were used to validate the model. The influence of wall material, pressure, mass flux, and wall temperature on the quench front velocity are correctly predicted. The REWET-2 and PERICLES experiments in rod bundle geometry were used to assess the capabilities of the code to predict simultaneous bottom and top-down rewetting. Comparison of the calculated results with the REWET 2 experimental data shows the ability of the new package to calculate the key features of this complex experiment. The existence and progression of two quench fronts in the core are correctly predicted. The maximum cladding temperatures are overpredicted for experiments with combined and upper plenum injection. This difference, which is attributed to a too severe countercurrent flow limit (CCFL) calculated by the code, does not exceed 150 C. With the top-down reflooding option, improved predictions of wall temperatures in the upper part of the core in the PERICLES tests with respect to the previous version of the code were obtained, since this part of the core was rewetted by top-down quenching
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 106
- Journal Issue
- 1
- Journal Page Range
- p. 46-59.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058433
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- C CODES; COMPUTER CALCULATIONS; COOLANTS; CORE FLOODING SYSTEMS; FUEL CANS; LOSS OF COOLANT; OPERATION; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; REWETTING; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DATA; ECCS; ENGINEERED SAFETY SYSTEMS; INFORMATION; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; SAFETY