Published July 1992 | Version v1
Report Metadata-only

Design bases and severe accident considerations for the System 80+ trademark containment design

Creators

  • 1. ABB-Combustion Engineering, Inc., Windson, CT (United States)
  • 2. Duke Engineering and Services, Inc., Charlotte, NC (United States)

Description

Containments for Advanced Light Water Reactors (ALWRs) must not only be designed for design bases conditions but also be evaluated for postulated severe accident concerns. This paper presents the containment design description for the System 80+ ALWR, the conservative design bases specified and the System 80+ ALWR design features to prevent and mitigate the challenges considered in postulated severe accident scenarios. Included in the containment design bases are postulated primary and secondary pipe break conditions and seismic requirements for an envelope of site conditions with a control motion having much higher energy content than those used for existing reactor designs. Severe accident considerations addressed include prevention and mitigation design features incorporated into the System 80+ ALWR

Additional details

Publishing Information

Imprint Title
Proceedings of the fifth workshop on containment integrity
Imprint Pagination
646 p.
Journal Page Range
p. 163-178.
Report number
NUREG/CP--0120

Conference

Title
5. workshop on containment integrity for nuclear power plants.
Dates
12-14 May 1992.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24027225
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BASEMENTS; COMBUSTION; CONSTRUCTION; CONTAINMENT SYSTEMS; CORIUM; DEPRESSURIZATION; DESIGN BASIS ACCIDENTS; DIESEL ENGINES; EARTHQUAKES; ELECTRIC BATTERIES; ELECTRIC GENERATORS; ENGINEERED SAFETY SYSTEMS; EXPLOSIONS; FEEDWATER; HYDROGEN; LOSS OF COOLANT; MELTDOWN; MITIGATION; OUTAGES; PRESSURIZATION; PRIMARY COOLANT CIRCUITS; PROBABILITY; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR FUELING; REACTOR MAINTENANCE; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR STABILITY; REGULATIONS; RELIABILITY; SECONDARY COOLANT CIRCUITS; SEISMIC EFFECTS; SOIL-STRUCTURE INTERACTIONS; STANDARDIZATION; TEMPERATURE DEPENDENCE; TIME DEPENDENCE
Descriptors DEC
ACCIDENTS; CHEMICAL REACTIONS; CONTAINMENT; COOLING SYSTEMS; ELECTRICAL EQUIPMENT; ELECTROCHEMICAL CELLS; ELEMENTS; ENERGY STORAGE SYSTEMS; ENGINES; ENRICHED URANIUM REACTORS; EQUIPMENT; HEAT ENGINES; HYDROGEN COMPOUNDS; LAWS; MAINTENANCE; NONMETALS; OPERATION; OXIDATION; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SEISMIC EVENTS; STABILITY; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
SAND--92-0173; CONF-920541--.