Determination of the end state of the Three Mile Island Unit 2 accident using neutron transport analysis
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6766385
- The Pennsylvania State Univ., Dept. of Nuclear Engineering, 231 Sackett Building, University Park, PA (US)
- Burns and Roe Inc., TMI Nuclear Station, P.O. Box 480, Middletown, PA (US)
Since the March 1979 accident, the source range monitors (SRMs) at Three Mile Island Unit 2 (TMI-2) have been reading several orders of magnitude higher than would be expected in a normal shutdown core. A study in which these anomalous SRM readings are analyzed and the cause determined is reported. Here, the DOT 4.3 two-dimensional transport code was used to simulate the SRM response and the response of an axial string of solid-state track recorders by modeling the neutronics of the damaged TMI-2 core. This modeling has indicated the presence of -- 10 tonnes of fuel material in the lower vessel plenum, a condition that was subsequently verified by direct observation. The computational model, the method of cross-section preparation, and an analysis of the various core neutron sources are described, as well as the results obtained from this effort.
- OSTI ID:
- 6766385
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 81:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of the source range monitor during the first four hours of the Three Mile Island Unit 2 accident
Analysis of the TMI-2 source range monitor during the TMI (Three Mile Island) accident
Using the source range monitor response to determine fuel relocation during the TMI-2 (Three Mile Island Unit 2) accident
Journal Article
·
Tue Jan 31 23:00:00 EST 1989
· Nuclear Technology; (USA)
·
OSTI ID:5678361
Analysis of the TMI-2 source range monitor during the TMI (Three Mile Island) accident
Technical Report
·
Mon Jun 01 00:00:00 EDT 1987
·
OSTI ID:5493513
Using the source range monitor response to determine fuel relocation during the TMI-2 (Three Mile Island Unit 2) accident
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:5321692
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
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
ENRICHED URANIUM REACTORS
FISSION TRACKS
MEASURING INSTRUMENTS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON ACTIVATION ANALYZERS
NEUTRON SOURCES
NEUTRON TRANSPORT
PARTICLE SOURCES
PARTICLE TRACKS
POWER REACTORS
PWR TYPE REACTORS
RADIATION SOURCES
RADIATION TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTOR SHUTDOWN
REACTORS
SHUTDOWNS
SIMULATION
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
TWO-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
ENRICHED URANIUM REACTORS
FISSION TRACKS
MEASURING INSTRUMENTS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON ACTIVATION ANALYZERS
NEUTRON SOURCES
NEUTRON TRANSPORT
PARTICLE SOURCES
PARTICLE TRACKS
POWER REACTORS
PWR TYPE REACTORS
RADIATION SOURCES
RADIATION TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTOR SHUTDOWN
REACTORS
SHUTDOWNS
SIMULATION
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
TWO-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS