Yankee Atomic Electric Company Research and Development Program: Quarterly Progress Report: October 1, 1958 to December 31, 1958 (open access)

Yankee Atomic Electric Company Research and Development Program: Quarterly Progress Report: October 1, 1958 to December 31, 1958

Quarterly report describing the technical research and development work accomplished by the Yankee Atomic Electric Company Research and Development Program, and documenting progress made on the group's various projects and goals.
Date: February 16, 1959
Creator: Garbe, R. W. & Walchli, H. E.
System: The UNT Digital Library
ROLLING AND WELDING TYPE 430M TUBES TO STAINLESS STEEL OVERLAID CARBON STEEL TUBE-SHEETS. SM-1 (APPR-1) RESEARCH AND DEVELOPMENT PROGRAM. Task No. X. (open access)

ROLLING AND WELDING TYPE 430M TUBES TO STAINLESS STEEL OVERLAID CARBON STEEL TUBE-SHEETS. SM-1 (APPR-1) RESEARCH AND DEVELOPMENT PROGRAM. Task No. X.

In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tubesheets to ASTM Specification A350-Grade LF-1, modifled with 1.66% nickel; and weld the tube ends to the stainless steel overlay previously applied to the tubesheet. The rolled joint was a necessary precaution to prevent secondary water, that might contain chlorides, from contacting the stainless steel weld joining the tubes to the tubesheets. The welded joint provided the mechanical strength for attaching the tubes to the tubesheets. A laboratory program was conducted, therefore, to develop practicable procedures for welding the Type 430M tubes to the stainless steel overlay; as well as to assure that the tubes could satisfactorily be rolled to the tubesheets. Automatic and manual tungstenare welding procedures were developed that were capable of consistently providing an austenitic weld having a strength exceeding that of the heat affected zone or the unaffected tube itself. Type 430M tubes in the asreceived, and softened conditions were rolled into prototype test units under various conditions of rolling. It was concluded that the Type 450M tubes in the as-received condition could be satisfactorily rolled into the A360Grade LF-1 tubesheet and be tlght …
Date: February 16, 1959
Creator: Bennett, R.W.; Meister, R.P. & Kerton, R.J.
System: The UNT Digital Library
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 (open access)

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

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 …
Date: February 16, 1959
Creator: Marshall, R. K.
System: The UNT Digital Library
Safeguard Report For Open Pool Reactor For State College of Washington (open access)

Safeguard Report For Open Pool Reactor For State College of Washington

This report presents the reactor description and safeguard evaluation for an open pool research and test reactor being supplied to the State College of Washington, Pullman, Washington, by the General Electric Company.
Date: February 16, 1959
Creator: Holzmann, E. G.
System: The UNT Digital Library
Particle Extraction III (open access)

Particle Extraction III

A device to extend the operation of a beam extraction system is described for low energies where the radiation loss per turn is ineffective. The device consists of a noisy radiofrequency field which excites the radial betatron oscillation
Date: February 16, 1959
Creator: Robinson, Kenneth W.
System: The UNT Digital Library