An account of the OECD LOFT (Organization for Economic Cooperation and Development Loss-of-Fluid) Project

Technical Report · Tue May 01 04:00:00 EDT 1990

DOI:https://doi.org/10.2172/6818147· OSTI ID:6818147

Fell, J ^[1]; Modro, S M ^[2]

---

1. UKAEA Headquarters, London (UK)
2. EG and G Idaho, Inc., Idaho Falls, ID (USA)

This report sets out the history and records the significant technical findings of a particularly important international collaboration on nuclear reactor safety, the OECD LOFT Project, in which a number of OECD countries, organized through the NEA, collaborated on a program to use of the LOFT (Loss-of Fluid Test) experimental nuclear test facility at the Idaho National Engineering Laboratory (INEL) in a program of safety experiments. The initial proposal was developed from an initiative of the United States Department of Energy, who also provided continuing management support. The objective of an international team with those of the reactor operation and analysis staff at INEL to provide a significant addition both to the international database of large-scale experimental data on reactor safety and to the analysis and understanding of the test results. 51 refs., 15 figs., 11 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6818147
• Report Number(s): OECD/LOFT-T-3907; ON: DE90013022
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOLS
COLLOIDS
COMPUTER CODES
COOLING SYSTEMS
COOPERATION
COORDINATED RESEARCH PROGRAMS
DATA
DISPERSIONS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EXPERIMENTAL DATA
FISSION PRODUCT RELEASE
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
INFORMATION
INTERNATIONAL COOPERATION
LOFT REACTOR
LOSS OF COOLANT
MANAGEMENT
MECHANICS
NUMERICAL DATA
PROGRAM MANAGEMENT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
SOLS
TANK TYPE REACTORS
TEST FACILITIES
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS