PT-IP-158-D, Supplement B: Irradiation of one swaged UO{sub 2} stainless steel clad fuel element in a KE front-to-rear test hole

Technical Report · Mon Feb 16 04:00:00 EST 1959

DOI:https://doi.org/10.2172/10171843· OSTI ID:10171843

Marshall, R K

The objective of this supplement is to authorize a change in the panellit trip range from 25--75 psi to 5--95 psi. The test hole facility consists of two concentric aluminum tubes which extend from the front face to the rear face of the reactor. The ID of the inner tube is 2--7/8 inch. Water from one crossheader supplies the annulus, water from another crossheader supplies the inner tube. The three-foot-long, .570 inch OD fuel element is centered in a 40-inch long aluminum holder which has an ID of 1.380 inch and an OD of 2.800 inch. The panellit gage which monitors the flow to the inner tube fluctuates to such an extent during start-up that on two occasions the reactor was scrammed. During equilibrium operation the panellit gage reading remains stable. A possible explanation of this behavior is that during start-up aluminum spacers which are in the inner tube as part of the test charge chatter and cause variations in the water path through the tube. It is further surmised that at equilibrium operation the pressure drop across the column in the tube is sufficient to suppress the chattering. It is concluded that extending the trip range to 5--95 psi will reduce the possibility of scramming without increasing any hazards to the reactor.

• 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: 10171843
• Report Number(s): HW--59264; ON: DE94016254
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
EXPERIMENTAL CHANNELS
FLOWMETERS
FUEL ELEMENTS
HANFORD PRODUCTION REACTORS
LIMITING VALUES
MECHANICAL VIBRATIONS
MITIGATION
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
REACTOR OPERATION
REACTOR START-UP
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
SCRAM
SPACERS
SPECIFICATIONS
URANIUM DIOXIDE