A thermodynamic envelope for containment pressure-temperature transients
Creators
- 1. Nuclear Engineering Program, Univ. of Maryland, College Park, MD
Description
Reactor containment pressurization due to a Class 9 or degraded core accident is strongly scenario dependent. In this study, an essentially scenario free upper limit pressure envelope for PWR dry containments is determined. It is assumed that all of the energy available during the event is released immediately to the containment at the time of its generation. The only energy removal is by energy transfer into passive heat sinks (concrete and steel). No active heat sinks, such as sprays or air coolers, are assumed. Pressure profiles are generated for a range of parameters: reactor power, containment free volume, and heat sink area and thickness. The effects of the rapid addition of stored energy on the containment pressure profile are analyzed
Additional details
Publishing Information
- Publisher
- A.S.M.E.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Advances in containment design and analysis
- Journal Page Range
- p. 31-36.
Conference
- Title
- 2. joint ASME/ANS nuclear engineering conference.
- Dates
- 25-28 Jul 1982.
- Place
- Portland, OR (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15049490
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONCRETES; CONTAINMENT SYSTEMS; ENERGY TRANSFER; HEAT SINKS; MULTI-PARAMETER ANALYSIS; PRESSURE GRADIENTS; REACTOR CORE DISRUPTION; STEELS; TEMPERATURE DEPENDENCE; THERMODYNAMICS; THICKNESS; TRANSIENTS; VOLUME
- Descriptors DEC
- ACCIDENTS; ALLOYS; BUILDING MATERIALS; CARBON ADDITIONS; CONTAINMENT; DIMENSIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; REACTOR ACCIDENTS