An improved RELAP5/MOD3.3 reflood model considering the effect of spacer grids
Creators
- 1. Reactor Core Technology Department, KEPCO Nuclear Fuel, 493 Deokjin-dong, Daejeon 305-353 (Korea, Republic of)
- 2. Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)
Description
Highlights: ► We modify the reflood heat transfer package of RELAP5/MOD3.3. ► We introduce a special model to consider the effect of spacer grids. ► The modified reflood model is assessed against various reflood tests. ► Cladding temperature behaviors are predicted much better with the modified model. - Abstract: Various efforts have been made to improve the models and correlations of RELAP5/MOD3.3, which are activated only during the reflood phase of a large break loss-of-coolant-accident, the so-called "reflood model". The film boiling heat transfer regime was divided into three sub-regimes and appropriate wall-to-fluid heat transfer coefficient correlations were applied to each sub-regime. The models for estimating the size and the velocity of droplets were also modified. In addition, we introduced a special model to take into account the wall-to-fluid or interfacial heat transfer enhancement due to the spacer grids. The modified reflood model was assessed against eight FLECHT-SEASET tests and six RBHT tests having various initial and boundary conditions. The modified reflood model better predicted the PCTs and quench times of the eight FLECHT-SEASET tests: the RMS deviation of PCT predictions was reduced from 51.7 K to 29.8 K and it was reduced from 81.9 s to 33.5 s in the case of quench time predictions. As for the six RBHT tests, the quench times were predicted much better by the modified reflood model while not much improvement in the PCT predictions was obtained: the RMS deviation in quench time predictions was reduced from 322.5 s to 132.1 s while the RMS deviation of PCT predictions were 62.5 K and 53.1 K before and after the modifications, respectively. Additional calculations were conducted excluding the spacer grid heat transfer enhancement model to reveal that the model is essential to predict correctly the cladding temperature behaviors in the upper part of the core.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2012.06.025Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2012.06.025;
- PII
- S0029-5493(12)00344-5;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 250
- Journal Page Range
- p. 613-625
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44025277
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- BOUNDARY CONDITIONS; CLADDING; DROPLETS; FILM BOILING; HEAT TRANSFER; LOSS OF COOLANT; R CODES; SPACERS; TEMPERATURE DEPENDENCE; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; BOILING; COMPUTER CODES; DEPOSITION; ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; MECHANICS; PARTICLES; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; SURFACE COATING
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.