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Title: FRAP T-6: an independent code assessment based on LOCA Simulation Test MT-1 in the NRU reactor. [PWR]

Technical Report ·
OSTI ID:6216167

The Fuel Rod Analysis Program - Transient FRAP-T6 was independently assessed through comparisons with experimental data obtained from a Loss-of-Coolant Accident (LOCA) simulation test performed in the National Research Universal (NRU) reactor. A concise computer code description is given and computer code calculations are compared with experimental data from materials deformation test MT-1. Results of these comparison are discussed for different boundary conditions and different mathematical models which describe the physical processes in the fuel rod.

Research Organization:
EG and G Idaho, Inc., Idaho Falls (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6216167
Report Number(s):
EGG-LOFT-6233; ON: DE83013373
Resource Relation:
Other Information: Portions are illegible in microfiche products
Country of Publication:
United States
Language:
English