Published May 2007 | Version v1
Journal article Metadata-only

The experimental study of heat transfer crisis in channels with twisted heat transferring rods

Creators

  • 1. Rossijskij Nauchnyj Tsentr Kurchatovskij Inst., Moscow (Russian Federation)

Description

The results of the experimental investigations of the hydraulic resistance and critical heat flows at the fuel assemblies mockups with the fuel elements simulators curled with regard to the longitudinal axis, with the transverse cross section of the three-beam shape are presented. The data of experiments are compared with results received in framework of the procedures, assumed for the design calculations of the WWER type reactors fuel element clusters

Abstract (Russian)

Приведены результаты экспериментальных исследований гидравлического сопротивления и критических тепловых потоков на моделях тепловыделяющих сборок с имитаторами твэлов, завитыми относительно продольной оси, с поперечным сечением трехлучевой формы. Проведено сравнение данных экспериментов с результатами, полученными по методикам, принятым для проектных расчетов пучков твэлов реакторов типа ВВЭР

Additional details

Additional titles

Original title (Russian)
Экспериментальное исследование кризиса теплоотдачи в каналах с витыми тепловыделяющими стержнями

Publishing Information

Journal Title
Teploehnergetika
Journal Issue
no.5
Journal Page Range
p. 50-52
ISSN
0040-3636
CODEN
TPLOA5

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
39095038
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
CONFIGURATION; CONTROL ELEMENTS; CRITICAL HEAT FLUX; CROSS SECTIONS; EXPERIMENTAL DATA; FUEL ASSEMBLIES; HEAT TRANSFER; HYDRAULICS; REACTOR CHANNELS; REACTOR SAFETY; RODS; SHAPE; THERMAL BOUNDARY RESISTANCE; WWER TYPE REACTORS
Descriptors DEC
DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT FLUX; INFORMATION; MECHANICS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs., 4 figs.