Published 1980 | Version v1
Report Metadata-only

Thermal hydraulics related to reactor safety

Creators

  • 1. Nuclear Regulatory Commission, Washington, DC

Description

The most critical concern of reactor safety is the availability of cooling capability, be it the coolant inventory or the ECC (Emergency Core Cooling) capability. Thus, thermal hydraulics of the reactor coolant is one of the most important topics of reactor safety. Many thermal hydraulic issues are encountered in postulated accident scenarios. The scenarios for major LOCA (Loss of Coolant Accidents) and for small break accidents are presented. Information is presented concerning interfacial heat transfer; interfacial mass transfer; and system effects

Additional details

Additional titles

Augmented title (English)
PWR;BWR

Publishing Information

Imprint Title
Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: PWR and BWR reactor-plant performance analysis and containment technology
Journal Page Range
p. 1-63.
Report number
NUREG/CP--0014(Vol.1)

Conference

Title
ANS/ASME topical meeting on reactor thermal-hydraulics.
Dates
9 - 12 Oct 1980.
Place
Saratoga, NY, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12641470
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; ECCS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION
Descriptors DEC
ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS