Description and assessment of structural and temperature models in the FRAP-T6 code. [PWR; BWR]
Conference
·
OSTI ID:5524687
The FRAP-T6 code was developed at the Idaho National Engineering Laboratory (INEL) for the purpose of calculating the transient performance of light water reactor fuel rods during reactor transients ranging from mild operational transients to severe hypothetical loss-of-coolant accidents. An important application of the FRAP-T6 code is to calculate the structural performance of fuel rod cladding. The capabilities of the FRAP-T6 code are assessed by comparisons of code calculations with the measurements of several hundred in-pile experiments on fuel rods. The results of the assessments show that the code accurately and efficiently models the structural and thermal response of fuel rods.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5524687
- Report Number(s):
- EGG-M-17582; CONF-830805-57; ON: DE84000836
- Country of Publication:
- United States
- Language:
- English
Similar Records
Cladding axial elongation models for FRAP-T6. [PWR; BWR]
FRAP-T6 code development
FRAP-T6: a computer code for the transient analysis of oxide fuel rods. [PWR; BWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5539450
FRAP-T6 code development
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6409588
FRAP-T6: a computer code for the transient analysis of oxide fuel rods. [PWR; BWR]
Technical Report
·
Wed Jun 01 00:00:00 EDT 1983
·
OSTI ID:6006179
Related Subjects
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