Published 2001 | Version v1
Book Metadata-only

Elongation of RBMK fuel rods in the course of thermomechanical interaction between fuel and cladding

Creators

  • 1. GNTs RF FEhI, Obninsk (Russian Federation)
  • 2. GUP NIKIEhT, Moscow (Russian Federation)

Description

The analysis accomplished for experimental data on kinetics of variation of the axial gap between fuel rods in the course of operation of nuclear plants 1 and 2 at the Ignalina NPP and the comparison with calculation results is given. On the basis of measurements an experimental dependence of thermomechanical elongation of RBMK fuel elements on the burnup during stationary operation of the reactor is established. An anomalous elongation of individual fuel rods in the course of loading fuel assemblies into operating reactor is revealed. The calculations performed show a good agreement with experimental results

Abstract (Russian)

Проведен анализ экспериментальных данных по кинетике изменения осевого зазора между твэлами в процессе работы 1 и 2 блоков Игналинской АЭС, и дано сравнение с результатами расчетов. На основании измерений получена экспериментальная зависимость термомеханического удлинения твэлов РБМК от выгорания в процессе стационарной работы реактора. Отмечено аномальное удлинение отдельных твэлов в некоторых ТВС, полученное в процессе загрузки в работающий реактор. Проведенные расчеты показали хорошее совпадение с результатами измерений
Part of:
The collection of reports of 6. Russian conference on reactor material science. Vol. 2. P. 1. Fuel assemblies, fuel elements, absorber members, zirconium materials for nuclear reactors

Additional details

Additional titles

Original title (Russian)
Удлинение твэлов реактора RBMK в процессе термомеханического взаимодействия топливо-оболочка

Publishing Information

Publisher
GNTs RF NIIAR
Imprint Place
Dimitrovgrad (Russian Federation)
ISBN
5-85165-651-4
Imprint Title
Collection of reports of 6. Russian conference on reactor material science. Vol. 2. P. 1. Fuel assemblies, fuel elements, absorber members, zirconium materials for nuclear reactors
Imprint Pagination
325 p.
Journal Page Range
p. 90-96, 97-103

Conference

Title
6. Russian conference on reactor material science
Original Conference Title
Shestaya Rossijskaya konferentsiya po reaktornomu materialovedeniyu
Dates
11-15 Sep 2000
Place
Dimitrovgrad (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
33057270
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; DIMENSIONS; ELONGATION; EVALUATION; FUEL ASSEMBLIES; FUEL CANS; FUEL ELEMENTS; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; IGNALINA-1 REACTOR; IGNALINA-2 REACTOR; STRESSES; THERMAL CYCLING
Descriptors DEC
DEFORMATION; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; PELLETS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS

Optional Information

Notes
4 refs., 7 figs., 1 tab. Imprint:Sbornik dokladov Shestoj Rossijskoj konferentsii po reaktornomu materialovedeniyu. Tom 2. Chast' 1. TVS, tvehly, pehly, tsirkonievye materialy dlya yadernykh reaktorov