Published 2015 | Version v1
Journal article Metadata-only

Experimental study of thermal and hydraulic characteristics of VK-300 reactor in solitary uptake tube model

Creators

  • 1. Obninskij Inst. Atomnoj Ehnergetiki NIYaU MIFI, Obninsk (Russian Federation)

Description

Authors present the realization of experimental works of thermohydraulic reactor characterization on the model of single draft tube. They show that there is a possible ingress of steam into the ring slit, modeling inter tubular space and its penetration into the nuclear reactor core inlet

Abstract (Russian)

В работе представлены экспериментальные исследования теплогидравлических характеристик реактора ВК-300 на модели одиночной тяговой трубы. Показана возможность попадания пара в кольцевую щель, моделирующую межтрубное пространство, и его проникновение на вход активной зоны

Additional details

Additional titles

Original title (Russian)
Экспериментальные исследования теплогидравлических характеристик реактора VK-300 на модели одиночной тяговой трубы

Publishing Information

Journal Title
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Journal Issue
no.2
Journal Page Range
p. 96-107
ISSN
0204-3327

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
48033231
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BWR TYPE REACTORS; FAST REACTORS; MIXTURES; NATURAL CONVECTION; NUCLEAR POWER; STEAM SEPARATORS; THERMAL HYDRAULICS
Descriptors DEC
CONVECTION; DISPERSIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EQUIPMENT; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; POWER; POWER REACTORS; REACTORS; SEPARATION EQUIPMENT; THERMAL REACTORS; VAPOR SEPARATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
8 refs., 6 figs.