Solution of the international benchmark with trip of one of four reactor coolant pumps for VVER-1000 reactor plants using the computer code package KORSAR/GP and complex reactor nodalization
Creators
- 1. EDO "GIDROPRESS", Podolsk (Russian Federation)
Description
The International OECD/NEA test benchmark for the trip of one of four operating reactor coolant pumps (RCPs) was solved using thermohydraulic code package KORSAR/GP. KORSAR/GP applies 1D calculational units. This benchmark was based on experimental results obtained during commissioning of Kalinin NPP, Unit 3. During the experiments a large amount of experimental data was obtained that enabled us to supplement the validation of the computer codes and nodalizations of 1D thermohydraulic codes. In the given transient there was a difference between coolant temperatures in different loops that resulted in the necessity of numerical simulation of the coolant mixing in the reactor plenums. To solve this problem, complex branched nodalization (i.e. the set of code calculational units) was used. The analysis results matched closely with the experimental data. Thus it was shown that the nodalization developed with the use of KORSAR/GP and the code itself can be applied for the simulation of VVER-1000 transients with one ore more RCPs in operation and sharp difference between coolant temperature in loops. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-05-6
- Imprint Title
- The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
- Imprint Pagination
- 766 Megabytes
- Journal Page Range
- [13 p.]
Conference
- Title
- 14. International Topical Meeting on Nuclear Reactor Thermalhydraulics
- Acronym
- NURETH-14
- Dates
- 25-30 Sep 2011
- Place
- Toronto, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 47071436
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature, Numerical Data
- Descriptors DEI
- COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; FLUID MECHANICS; KALININ-3 REACTOR; THERMAL HYDRAULICS; WWR TYPE REACTORS
- Descriptors DEC
- DATA; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; INFORMATION; MECHANICS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Paper NURETH14-295, 7 refs., 2 tabs., 10 figs.