Published 2013 | Version v1
Journal article Metadata-only

Numerical and experimental investigation of the model steam generator reactor facility BREST-OD-300

Creators

  • 1. GNTs RF-Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo, Obninsk (Russian Federation)
  • 2. OAO Nauchno-Issledovatel'skij i Konstruktorskij Inst. Ehnergotekhniki imeni N.A. Dollezhalya, Moscow (Russian Federation)

Description

The paper presents the results of testing the three-tubes model of steam generator reactor facility BREST-OD-300, heated by liquid lead, at subcritical (18 MPa) and supercritical (25 MPa) pressure of the water at a flowrate 80, 100 and 120% of the nominal value

Abstract (Russian)

Приводятся результаты испытания трехтрубной модели парогенератора РУ БРЕСТ-ОД-300, обогреваемой свинцом, при докритическом (18 МПа) и сверхкритическом (25 МПа) давлении в водяном контуре при расходах воды 80, 100 и 120% от номинального значения

Additional details

Additional titles

Original title (Russian)
Расчетно-экспериментальное исследование работы модели парогенератора BREST-OD-300

Publishing Information

Journal Title
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Journal Issue
no.1
Journal Page Range
p. 101-109
ISSN
0204-3327

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
47114867
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
COOLANTS; CRITICAL PRESSURE; FAST REACTORS; LEAD; NUCLEAR POWER; PRESSURE CONTROL; STEAM GENERATORS; TEMPERATURE DISTRIBUTION
Descriptors DEC
BOILERS; CONTROL; ELEMENTS; EPITHERMAL REACTORS; METALS; PHYSICAL PROPERTIES; POWER; REACTORS; THERMODYNAMIC PROPERTIES; VAPOR GENERATORS

Optional Information

Notes
5 refs., 6 figs., 3 tabs.