Probabilistic determination of neutronic trip setpoints at Cernavoda NPP, Romania
Description
This paper describes the methodology used for probabilistic determination of the Regional Overpower tripsetpoints at Cernavoda Nuclear Power Plant Unit 1 (a CANDU project). The shutdown systems use in-core flux detectors to protect against local power increases that can lead to fuel dryout and melting. These flux detectors are spread throughout the reactor core and are assigned to 3 independent trip channels per shutdown systems. The design criteria is that each shutdown system must trip the reactor with a confidence of 98% on a 2 of 2 logic, i.e. assuming the best trip channel unavailable. Parameter considered in the calculation of the trip-setpoints (TSP) are affected by random and systematic error. The probabilistic approach described here was developed by AECL specialists and allows error margins of ∼ 10%, lower than the deterministic margin of 15-20%.(author)
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Additional details
Publishing Information
- Publisher
- Nuclear Society of Slovenia
- Imprint Place
- Ljubljana (Slovenia)
- ISBN
- 961-6207-13-X
- Imprint Title
- International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings
- Imprint Pagination
- 683 p.
- Journal Page Range
- p. 439-444
- Report number
- INIS-SI--02-002
Conference
- Title
- International Conference on Nuclear Energy in Central Europe 99
- Dates
- 6-9 Sep 1999
- Place
- Portoroz (Slovenia)
INIS
- Country of Publication
- Slovenia
- Country of Input or Organization
- Slovenia
- INIS RN
- 33071046
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; CERNAVODA-1 REACTOR; DISTRIBUTION; PROBABILISTIC ESTIMATION; REACTOR SHUTDOWN; SAFETY; SCRAM; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; THERMAL REACTORS
Optional Information
- Notes
- 2 refs., 4 figs.