Behavior of Defective PWR Fuel Rods During Power Ramp and Film Boiling Operation
Title | Behavior of Defective PWR Fuel Rods During Power Ramp and Film Boiling Operation PDF eBook |
Author | Douglas W. Croucher |
Publisher | |
Pages | 44 |
Release | 1979 |
Genre | Nuclear fuel rods |
ISBN |
Energy Research Abstracts
Title | Energy Research Abstracts PDF eBook |
Author | |
Publisher | |
Pages | 520 |
Release | 1979 |
Genre | Power resources |
ISBN |
NUREG/CR.
Title | NUREG/CR. PDF eBook |
Author | U.S. Nuclear Regulatory Commission |
Publisher | |
Pages | 148 |
Release | 1980 |
Genre | Nuclear energy |
ISBN |
Transportation of Radionuclides in Urban Environs, Environmental Assessment (EA)
Title | Transportation of Radionuclides in Urban Environs, Environmental Assessment (EA) PDF eBook |
Author | |
Publisher | |
Pages | 598 |
Release | 1980 |
Genre | |
ISBN |
Fuel Rod Failure During Film Boiling (PCM-1 Test in the PBF). [PWR].
Title | Fuel Rod Failure During Film Boiling (PCM-1 Test in the PBF). [PWR]. PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 1978 |
Genre | |
ISBN |
The Power-Cooling-Mismatch (PCM) Test, PCM-1 was conducted in the Power Burst Facility (PFB) in March of 1978. The PCM Test Series is being conducted at the Idaho National Engineering Laboratory by EG and G Idaho, Inc., under contract to the USNRC and is designed to characterize the behavior of nuclear fuel rods operating under conditions of high power or low coolant flow or both leading to departure from nucleate boiling. The PCM-1 test was performed to provide in-pile data for a ''worst case'' PCM incident. The objective of this experiment was to study the behavior of a single pressurized water reactor (PWR) fuel rod subjected to a high-power and low flow environment which would result in cladding failure at full power. The ''worst case'' conditions established for the experiment consisted of a rod peak power of 78.7 kW/m and a coolant mass flux of 1356 kg/s.m2. Fuel temperatures at the stipulated operating conditions were such that a significant volume of molten fuel was present when failure occurred which produced a high probability of molten fuel-coolant interaction (MFCI) with the possibility of a vapor explosion.
Title List of Documents Made Publicly Available
Title | Title List of Documents Made Publicly Available PDF eBook |
Author | |
Publisher | |
Pages | 880 |
Release | |
Genre | Nuclear power plants |
ISBN |
Regulatory and Technical Reports
Title | Regulatory and Technical Reports PDF eBook |
Author | U.S. Nuclear Regulatory Commission. Division of Technical Information and Document Control |
Publisher | |
Pages | 378 |
Release | 1979 |
Genre | Nuclear energy |
ISBN |
Includes indexes.