Summary of Meeting
Description
The V1000CT benchmark defines standard problems for validation of coupled three-dimensional (3-D) neutron-kinetics/system thermal-hydraulics codes for application to Soviet-designed VVER-1000 reactors using actual plant data without any scaling. The overall objective is to access computer codes used in the safety analysis of VVER power plants, specifically for their use in reactivity transient simulations in a VVER-1000. The V1000CT benchmark consists of two phases: V1000CT1 - simulation of the switching on of one main coolant pump (MCP) while the other three MCP are in operation, and V1000CT2 - calculation of coolant mixing tests and Main Steam Line Break (MSLB) scenario. MSLB simulation is the objective of V1000CT2 Exercises 2 and 3, respectively using vessel boundary conditions and full plant model. The technical topics presented at this meeting were as follows: - Clarify the cross-sections for V1000CT2 Exercises 2 and 3; - Present and discuss the results of V1000CT2 Exercises 2; - Present and discuss the results of V1000CT2 Exercises 3; - Update the work plan and actions. The Agenda is provided as Annex I
Files
45073540.pdf
Files
(73.4 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:af6178ae303cc9b8ac5088e250f59f80
|
73.4 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- NEA-NSC-DOC--2006-21
Conference
- Title
- Ad-hoc Meeting for the OECD/DOE/CEA VVER-1000 Coolant Transient Benchmark
- Acronym
- V1000-CT4.5
- Dates
- 12 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 45073540
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; CROSS SECTIONS; FLOW MODELS; MESH GENERATION; NUCLEAR DATA COLLECTIONS; PRESSURE DROP; PRESSURE VESSELS; STEAM GENERATORS; THERMAL HYDRAULICS; TRANSIENTS; WWER TYPE REACTORS
- Descriptors DEC
- BOILERS; CONTAINERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL MODELS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS