Parallelization of subchannel thermal-hydraulic code CTF of reactor core based on domain decomposition
Creators
- 1. Department of Engineering Physics, Tsinghua University, Beijing (China)
Description
CTF (Coolant Boiling in Rod Arrays-Two Fluid) is a new sub-channel thermal/hydraulic simulation code developed by CASL (The Consortium for Advanced Simulation of Light Water Reactors) and PSU (Pennsylvania State University). It can solve steady or transient-state problems efficiently for both single assembly and full-core reactor. Thus, this code solves the computational efficiency and memory consumption problems effectively. First, CTF computes the BEAVRS benchmark in parallel with the domain decomposition technology. The power data which CTF uses are calculated by RMC(a Monte Carlo code for reactor core analysis). After calculating for 268 s, we get detailed fuel pin temperature, water temp and density output results. Accordingly, the efficiency and reliability of CTF is verified. On this basic work of CTF calculation for BEAVRS benchmark,the coupling between RMC and CTS for full-core problem will achieved soon. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- High Power Laser and Particle Beams
- Journal Volume
- 29
- Journal Issue
- 1
- Journal Page Range
- [6 p.]
- ISSN
- 1001-4322
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 51096363
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BOILING; COOLANTS; DENSITY; EFFICIENCY; FLUIDS; FUEL PINS; FUEL RODS; MONTE CARLO METHOD; REACTOR CORES; RELIABILITY; SIMULATION; THERMAL HYDRAULICS; TRANSIENTS; WATER MODERATED REACTORS
- Descriptors DEC
- CALCULATION METHODS; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; MECHANICS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 7 figs., 4 tabs., 8 refs.; http://dx.doi.org/10.11884/HPLPB201729.160221