Modeling of continuous withdrawal and falling out of CPS control rods accident, using QUABOX/CUBBOX-HYCA code
Creators
- 1. Lithuanian Energy Institute, Kaunas (Lithuania)
Description
At present, at the Ignalina NPP the process of a wider use of the new uranium-erbium fuel of higher saturation and the manual control rods of new design is going on. These actions are directed to reducing the reactor control and protection system (CPS) cooling circuit voiding effect and to improving the technical and economical reactor operation parameters. Continuous withdrawal and falling out of CPS control rods lead to the reactivity and power changes in the reactor core. Therefore, important for safety is the evaluation of the CPS ability to compensate for the resulting excess reactivity in the reactor core, having the changed core loading conditions during such accidents. This article presents the calculation results of the continuous withdrawal and falling out of CPS control rods for the specific reactor core conditions of the Ignalina NPP Unit 2, i.e. during its operation on the maximum allowed power level of 4200 MW. The German code QUABOX/CUBBOX-HYCA with the improved CPS logic was used for the simulation of the above-mentioned transients. (author)
Additional details
Additional titles
- Original title (Russian)
- Моделирование аваринои ситуаcии с самоходами и падением стерзнеи SUZ с помосcйу програмного комплекса QUABOX/CUBBOX-HYCA
Publishing Information
- Journal Title
- Lietuvos Mokslu Akademija. Energetika
- Journal Issue
- no.3
- Journal Page Range
- p. 11-20
- ISSN
- 0235-7208
INIS
- Country of Publication
- Lithuania
- Country of Input or Organization
- Lithuania
- INIS RN
- 34066203
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; IGNALINA-1 REACTOR; IGNALINA-2 REACTOR; NUMERICAL DATA; REACTOR CORES; REACTOR PROTECTION SYSTEMS; ROD DROP METHOD; RODS
- Descriptors DEC
- DATA; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; INFORMATION; LWGR TYPE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS
Optional Information
- Notes
- 7 refs., 4 figs., 5 tabs.