Results of the QUENCH-12 reflood experiment with a VVER-type bundle
Creators
- 1. Forschungszentrum Karlsruhe GmbH, Institut fuer Materialforschung, Karlsruhe (Germany)
Description
The QUENCH-12 experiment investigated the effects of VVER materials and bundle geometry on core reflood, in comparison with test QUENCH-06 (ISP-45) with western PWR geometry. While the PWR bundle simulator is made of a single unheated rod, 20 heated rods, and 4 corner rods arranged on a square lattice, the VVER bundle uses 13 unheated rods, 18 heated rods and 6 corner rods, arranged on a hexagonal lattice. The test was conducted with broadly the same protocol as QUENCH-06, so that the effects of VVER characteristics could be more easily observed. Ths involved pre-oxidation to a maximum of about 200 μm oxide thickness at a temperature of about 1200degC, followed by a power ramp until a temperature of 1800degC was reached, then reflood with water at room temperature was initiated. The test was successfully conducted at the Karlsruhe Research Center on 27 September 2006 in the frame of ISTC project 1648.2. The determination of the test protocol was based on numerous calculations with SCDAP/RELAP5, SCDAPSIM and ICARE/CATHARE. The amount of hydrogen released in the quench phase (24 g) is six times higher than in QUENCH-06. This may be attributed to the longer excursion time, damaging of the cladding surfaces due to the breakaway oxidation and oxidation of locally formed melt. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [7 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39048646
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORE FLOODING SYSTEMS; FUEL CANS; FUEL ELEMENT CLUSTERS; HEXAGONAL CONFIGURATION; HYDROGEN; MOLTEN METAL-WATER REACTIONS; NIOBIUM; OXIDATION; REACTOR ACCIDENTS; SOURCE TERMS; TRANSIENTS; WWER TYPE REACTORS; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; CONFIGURATION; ECCS; ELEMENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; METALS; NONMETALS; POWER REACTORS; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; REFRACTORY METALS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name Final Paper, Paper ID ICONE15-10257.pdf; 2 refs., 16 figs.