Published 1997 | Version v1
Report Open

Analysis of fuel element cans seals in operating reactors

Creators

Description

Analysis of fuel element seals in operating reactor by measuring fission product concentrations in reactor WWER-1000 primary coolant circuit was performed. Using the modern physical models of fission product yields from irradiated fuel pellets, a set of computer programs was created. It permits to model the total process from fission products formation in irradiated fuels, and to determination of types and volumes of defects in operating reactor fuel cans. 13 refs., 4 tab., 17 figs

Availability note (English)

Available from INIS in electronic form

Files

30043678.pdf

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Additional details

Additional titles

Original title (Russian)
Анализ герметичности оболочек твэлов в работающем реакторе

Publishing Information

Imprint Pagination
36 p.
Report number
KFTI--97-8

INIS

Country of Publication
Ukraine
Country of Input or Organization
Ukraine
INIS RN
30043678
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTERIZED SIMULATION; COOLANTS; FISSION PRODUCTS; FUEL CANS; FUEL ELEMENTS; FUEL PELLETS; IODINE ISOTOPES; PRESSURIZATION; PRIMARY COOLANT CIRCUITS; WWER-5 REACTOR
Descriptors DEC
COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POWER REACTORS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS