Published 1999 | Version v1
Book Metadata-only

Studying the characteristics of passive systems for fast reactor emergency shutdown

Creators

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

Description

The characteristics of the system for fast reactor emergency shutdown are studied basing on calculations confirmed by experimental data. The system fast response and working displacement value, as well as the operational factors (coolant flow rate, its temperature increasing rate) are determined. The passive type system operates when sodium coolant temperature at reactor core outlet exceeds the threshold value. It is designed for the BN-600 reactor emergency protection. It is shown that the system operation time amounts to 9-12 s when simulating the conditions in the most dangerous fuel assembly under maximum credible design basis accident in the BN-800 reactor. This ensures time period two times greater than that required for reaching the temperature of sodium boiling initiation

Abstract (Russian)

На основе расчетов, подтвержденных экспериментальными данными, исследованы характеристики устройства для аварийного останова реактора на быстрых нейтронах. Определены инерционность и величина рабочего хода устройства, а также эксплуатационные факторы (скорость и темп роста температуры теплоносителя). Устройство пассивного типа срабатывает при превышении порогового значения температуры выходящего из активного зоны натрия. Оно разработано для аварийной защиты реактора БН-600. Показано, что при моделировании условий работы наиболее напряженной ТВС при запроектной аварии реактора БН-800 срабатывание устройства происходит за 9-12 с. Это обеспечивает двукратный запас по времени достижения температуры кипения натрия
Part of:
30 years of the BOR-60 reactor facility operation. Collection of the seminar abstracts

Additional details

Additional titles

Original title (Russian)
Izuchenie kharakteristik passivnykh ustrojstv avarijnogo ostanova reaktora na bystrykh nejtronakh

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. 32

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
32043949
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BN-800 REACTOR; BOILING; COOLANTS; EMERGENCY PLANS; MAXIMUM CREDIBLE ACCIDENT; REACTOR PROTECTION SYSTEMS; REACTOR SHUTDOWN; SODIUM; TEMPERATURE RANGE 1000-4000 K
Descriptors DEC
ACCIDENTS; ALKALI METALS; BREEDER REACTORS; DESIGN BASIS ACCIDENTS; ELEMENTS; ENGINEERED SAFETY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; METALS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SHUTDOWN; SODIUM COOLED REACTORS; TEMPERATURE RANGE

Optional Information

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