Heat transfer experiments simulating a failure of the inlet piping to a BDF reactor process tube

Technical Report · Wed Aug 16 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/10145645· OSTI ID:10145645

Waters, E. D.; Kreiter, M. R.

Laboratory heat transfer experiments were conduced to investigate fuel element temperatures which could result from coolant flow loss following a failure of the inlet piping to a process tube at a B, D, F, DR, or H reactor. The results are reported herein. Failure of the inlet coolant piping between the front header and the process tube on a reactor would stop the normal flow of cooling water to the fuel elements. Such a failure should immediately initiate a reactor shutdown, but the only means of removing the heat released during the post-shutdown period would be by reverse flow of hot water from the rear cross header. The subject experiments were conducted to determine what rear header pressure would be required to achieve adequate cooling of a BDF type reactor fuel assembly following such a piping rupture. Experimental studies were previously reported concerning failure of inlet piping to a K reactor geometry. The analytical techniques and experimental procedures used previously were also used in the present experiments.

• Research Organization: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10145645
• Report Number(s): HW--70769; ON: DE94010522
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300
220600
220900
FAILURES
FUEL ELEMENTS
HANFORD PRODUCTION REACTORS
HEAT TRANSFER
LOSS OF COOLANT
REACTOR CHANNELS
REACTOR SAFETY
REACTOR SHUTDOWN
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
RUPTURES