Published 1999 | Version v1
Book Metadata-only

Problems of thermal-hydraulic processes simulation under liquid metal natural convection in fast sodium cooled reactor tank using the water

Creators

  • 1. Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Fiziko-Ehnergeticheskij Inst. im. akad. A.I.Lejpunskogo, Obninsk (Russian Federation)

Description

The differential equations in the Bussinesck approximation applied for mathematical simulation of after-heat removal under natural convection in the fast sodium cooled reactor top chambers in a case of the reactor emergency shutdown are briefly considered. The similarity criteria for unsteady process of natural convection are obtained. A simple transparent water-filled model is used for checking fulfillment of the thermal similarity rules under conditions of transients, heat exchangers operation and different power levels (Peclet numbers)

Abstract (Russian)

Кратко рассмотрены дифференциальные уравнения в приближении Буссинеска, используемые для математического моделирования отвода остаточного тепловыледения при естественной конвекции в верхних камерах быcтрых реакторов с жидкометаллическим охлаждением при аварийной остановке реакторов. Получены критерии подобия для нестационарного процесса естественной конвекции. Для проверки выполнения правил теплового подобия при переходном режиме, при работе теплообменников и разных уровнях мощности (числах Пекле) использована простая прозрачная водяная модель
Part of:
30 years of the BOR-60 reactor facility operation. Collection of the seminar abstracts

Additional details

Additional titles

Original title (Russian)
Проблемы моделирования водой теплогидравлических процессов при естественной конвекции жидких металлов в баке реактора на BN

Publishing Information

Publisher
Gosudarstvennyj Nauchnyj Thentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov
Imprint Place
Dimitrovgrad (Russian Federation)
ISBN
5-85165-377-9
Imprint Title
30 years of the BOR-60 reactor facility operation. Collection of the seminar abstracts
Imprint Pagination
48 p.
Journal Page Range
p. 23-24

Conference

Title
30 years of the BOR-60 reactor facility operation
Original Conference Title
30 let ehkspluatatsii reaktornoj ustanovki BOR-60
Dates
8-9 Dec 1999
Place
Dimitrovgrad (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
32043945
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; DIFFERENTIAL EQUATIONS; ECCS; FUNCTIONAL MODELS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; NATURAL CONVECTION; SCALING LAWS; SIMULATION; WATER
Descriptors DEC
BREEDER REACTORS; CONVECTION; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; MASS TRANSFER; OXYGEN COMPOUNDS; REACTOR PROTECTION SYSTEMS; REACTORS; REMOVAL

Optional Information

Notes
1 fig. Imprint:30 let ehkspluatatsii reaktornoj ustanovki BOR-60. Sbornik referatov seminara