Published January 12, 1993 | Version v1
Miscellaneous Metadata-only

ROSA-III/923, BWR Rig of Safety Assessment for LOCA

Creators

Description

Description of test facility: ROSA-III is a 1/124 scaled down test facility with electrically heated core designed to study the response of engineered safety features to loss-of-coolant accidents in in commercial BWR. It consists of the following, fully instrumented subsystems: (a) the pressure vessel with a core simulating four half-length fuel assemblies and control rod; (b) steam line and feed water line, which are independent open loops; (c) coolant recirculation system, which consists of two loops provided with a recirculation pump and two jet pumps in each loop; (d) emergency cooling system, including HPCS, LPCS, LPCI, and ADS

Availability note (English)

Available on-line: http://www.nea.fr/abs/html/csni0047.html

Additional details

Identifiers

URL
http://www.nea.fr/abs/html/csni0047.html;

Publishing Information

Imprint Pagination
[html]

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40013872
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Computer Program Description, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; COMPUTER PROGRAM DOCUMENTATION; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; COOLING SYSTEMS; FUEL ASSEMBLIES; LOSS OF COOLANT; LOW PRESSURE COOLANT INJECTION; PRESSURE VESSELS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; RISK ASSESSMENT; STEAM LINES; TEST FACILITIES; TRANSIENTS; WEBSITES
Descriptors DEC
ACCIDENTS; CONTAINERS; DOCUMENT TYPES; ECCS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; PIPELINES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref.