Abstract
By use of the TOODEE2-J computer program, an analysis was carried out of the fuel rod behavior, and core damage was estimated for the TMI-2 reactor during the first three hours of the accident on March 28, 1979. The boundary conditions (e.g. core mixture level, steam flow rate and core inlet flow) are based on a thermal-hydraulic analysis by the RELAP4/MOD6/U4/J2 computer program. The calculated results suggest that bursting of almost all rods except peripheral low-powered rods occurred, and that a large part of the zircaloy cladding exceeded the eutectic temperature to form a liquid phase of ZrUO. A total of 43.5% of the zircaloy in the fueled part of the core had been converted to zirconium-dioxide by three hours into the accidient, and major damage to the fuel rods had also occured by then.
Original language | English |
---|---|
Pages (from-to) | 37-42 |
Number of pages | 6 |
Journal | Nuclear Engineering and Design |
Volume | 69 |
Issue number | 1 |
DOIs | |
Publication status | Published - 1982 Apr 2 |
Externally published | Yes |
ASJC Scopus subject areas
- Energy Engineering and Power Technology
- Nuclear Energy and Engineering
- Civil and Structural Engineering
- Mechanical Engineering
- Safety, Risk, Reliability and Quality