Published 1997 | Version v1
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The behaviour of water-cooled reactor fuel rods in steady state and transient conditions

Creators

  • 1. Institute of Atomic Energy, Otwock-Swierk (Poland)

Description

In this report, the results of temperature field and filling gas pressure calculations by means of contemporary calculational models for a WWER-440 and WWER-1000 type fuel rod at low and high burnup operating under steady-state conditions are presented. A review of in-core temperature and pressure measurements for various types of LWR fuel is also included. Basing on calculational and collected measured data, the behaviour of fuel cladding during large and small break LOCA, is estimated with special emphasis on their oxidation and failure resistance. (author)

Availability note (English)

Available from INIS in electronic form

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Additional details

Additional titles

Original title (Polish)
Zachowanie sie pretow paliwowych reaktorow chlodzonych woda w stanach ustalonych i nieustalonych

Publishing Information

Imprint Pagination
52 p.
Report number
IAE--25/A

INIS

Country of Publication
Poland
Country of Input or Organization
Poland
INIS RN
29065674
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
FUEL RODS; FUEL-CLADDING INTERACTIONS; MOLTEN METAL-WATER REACTIONS; OXIDATION; REACTOR COOLING SYSTEMS; REACTOR SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER-3 REACTOR; WWER-5 REACTOR
Descriptors DEC
CHEMICAL REACTIONS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information

Notes
38 refs, 40 figs, 15 tabs