Cladding tube deformation and core emergency cooling in a loss of coolant accident of a pressurized water reactor
Creators
- 1. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorbauelemente
Description
The paper summarizes the dominant effects which finally ensure the core coolability of a pressurized water reactor in a loss-of-coolant accident (LOCA). The main results are summarized as follows: The cooling effect of the two-phase mixture which is intensified during reflooding increases temperature differences on the cladding tube circumference and thus limits the mean circumferential burst strains to values of about 50%. An unidirected flow through the fuel rod bundle during the refill and reflooding phases causes maximum cooling channel blockage of about 70%. The coolability of deformed fuel elements can be maintained up to flow blockages of about 90%. All effects investigated indicate that in a LOCA no impairment of core coolability and public safety has to be expected. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 103
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 55-64
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- Concluding colloquium of the Projekt Nukleare Sicherheit (PNS) of the Kernforschungszentrum Karlsruhe G.m.b.H.
- Original Conference Title
- Abschlusskolloquium des Projektes Nukleare Sicherheit (PNS) des Kernforschungszentrums Karlsruhe G.m.b.H
- Dates
- 10-11 Jun 1986.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19009252
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; DEFORMATION; ECCS; ENRICHED URANIUM REACTORS; FUEL CANS; LOSS OF COOLANT; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Also published in report KFK--4170.