Optimal number of axial nodes in a faster-running DNBR program for an on-line application
- 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
- 2. Doosan Heavy Industries and Construction Company, Gyeonggi-do (Korea, Republic of)
Description
A faster-running thermal-hydraulic program was developed initially for the on-line calculation of the Departure from Nucleate Boiling Ratio (DNBR) in a pressurized water reactor core. It calculates the minimum DNBR (MDNBR) based on a four-channel core model using three-dimensional transport coefficients and prediction-correction solution scheme. Using a reference faster-running DNBR program, the variation of the MDNBR was examined for the axial nodal sections of 10, 20, 30 and 40. It was found that the relative MDNBR error increases and the MDNBR value is over-predicted as the number of axial nodes decreases. The relative MDNBR error was found to increase significantly if the number of axial nodes is less than 20. It is recommended for a faster-running DNBR program to use more than 20 axial nodes for an accuracy as well as a faster running. (author)
Additional details
Publishing Information
- Imprint Title
- NTHAS6: Proceedings of the 6th Japan-Korea symposium on nuclear thermal hydraulics and safety
- Imprint Pagination
- 818 p.
- Journal Page Range
- [5 p.]
Conference
- Title
- 6. Japan-Korea symposium on nuclear thermal hydraulics and safety
- Acronym
- NTHAS6
- Dates
- 24-27 Nov 2008
- Place
- Nago, Okinawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43053517
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCURACY; C CODES; COMPUTER CALCULATIONS; DEPARTURE NUCLEATE BOILING; ERRORS; FINITE DIFFERENCE METHOD; NODAL EXPANSION METHOD; ON-LINE SYSTEMS; OPTIMIZATION; PWR TYPE REACTORS; REACTOR CHANNELS; REACTOR CORES; THERMAL HYDRAULICS
- Descriptors DEC
- BOILING; CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; MECHANICS; NUCLEATE BOILING; NUMERICAL SOLUTION; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This USB flash memory can be used for WINDOWS 2000/XP, MACINTOSH 9.x/10.x; Acrobat Reader is included; Data in PDF format, Folder Name: FullPaper, Paper ID: N6P1026.pdf; 8 refs., 4 figs., 2 tabs.