Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

DEVELOPMENT OF A VARIABLE ORIFICE FOR HNPF FUEL CHANNELS

Technical Report ·
DOI:https://doi.org/10.2172/4004677· OSTI ID:4004677

Control of the exit temperature of the coolant from each fuel channel of the Hallam Nuclear Power Facility reactor is obtained by adjusting the coolant flow rate by a remotely operated variable orifice. Two variable orifices were designed and the hydraulic characteristics determined. Both orifice designs utilized a tapered plug moving in and out of a restricted flow passage at the upper end of the fuel channel. Data were obtained on pressure drop as a function of flow rate at different orifice plug positions; all measurements were made using water, and data were converted to equivalent values for sodium. Either type of orifice was capable of adjusting flow rate to match the power output of a fuel element at any location in the reactor core. The temperature sensitivity (change in exit temperature per unit change in orifice plug position) of the first type of orifice was low (lO deg F/in.) when used in combination with a central fuel element, and high (7OO deg F/in.) when used with a peripheral element. The temperature sensitivity of the second type was more uniform (varying from 90 to 250 deg F/ in.). Consequently, the second type of orifice was selected for the HNPF. (auth)

Research Organization:
Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
Sponsoring Organization:
USDOE
DOE Contract Number:
AT(11-1)-GEN-8
NSA Number:
NSA-15-019032
OSTI ID:
4004677
Report Number(s):
NAA-SR-5369
Country of Publication:
United States
Language:
English

Similar Records

HYDRAULIC CHARACTERISTICS OF A SHIELD PLUG ORIFICE
Technical Report · Wed May 23 00:00:00 EDT 1962 · OSTI ID:4752604

HYDRAULIC TESTS OF A PROTOTYPE HALLAM FUEL ELEMENT (SU-9) TO BE TESTED IN SRE
Technical Report · Sun Mar 12 23:00:00 EST 1961 · OSTI ID:4036376

HYDRAULIC CHARACTERISTICS OF HNPF 8-ROD FUEL ELEMENT
Technical Report · Thu Aug 15 00:00:00 EDT 1963 · OSTI ID:4673380