The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development (open access)

The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development

The SNAP II boilers which were designed are summarized. As shown by test results from the three boilers which were tested, a continuous progress in design was achieved. These designs were based on test data from both the SNAP I and SNAP II programs. As the quantity of data increased, physical models describing the heat transfer process were developed. These physical models provide the necessary correlation parameters which permit the extension of existing data to advanced design. Preliminary test sections were designed on the assumption that an allvapor nmodel which ignores the presence of the liquid phase during forced convection boiling could be used to describe the process quantitatively. The conventional Dittus-Boelter equation was applied with the increase in the vapor flow along the tube being ascribed to liquid evaporation. The assumption led to a design that fell short by about an order of magnitude since the exit qualities were only in the range of 10%, far less than required for complete vaporization. As a result, a revision in the concept of the mechanics of boiling was found necessary and a theoretical analysis was formulated, based on a dry wall'' or dropwise'' type boiling phenomenon. The test results of the …
Date: July 17, 1961
Creator: Gido, R. G.; Koestel, A.; Haller, H. C.; Huber, D. D. & Deibel, D. L.
System: The UNT Digital Library
Parametric analysis of Hanford speed of control criterion (open access)

Parametric analysis of Hanford speed of control criterion

This report examines the many interrelated nuclear, physical, and mechanical phenomena and actions which take place following a loss-of-coolant accident in a Hanford reactor operating at equilibrium power.
Date: July 17, 1961
Creator: Nilson, R.; Tiller, R. E. & Peden, J. C.
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program: Suggested Values for the Partial Cross Sections of U²³⁵ for Use in the Neutronic Analysis of Thermal and Intermediate Reactors (open access)

Maritime Gas-Cooled Reactor Program: Suggested Values for the Partial Cross Sections of U²³⁵ for Use in the Neutronic Analysis of Thermal and Intermediate Reactors

From abstract: In this report a consistent set of U-235 partial cross sections for use in the analysis of thermal or intermediate reactor systems has been provided.
Date: July 17, 1961
Creator: Goodjohn, A. J. & Wikner, N. F.
System: The UNT Digital Library
Internal Conversion Coefficients of the 2+-0+, E2 Transitions in Even-Even Sm152[over]90 and Gd152[over]88 (open access)

Internal Conversion Coefficients of the 2+-0+, E2 Transitions in Even-Even Sm152[over]90 and Gd152[over]88

From abstract: "To investigate the deviation of the internal conversion coefficients of E2 transitions from theoretical computations and their dependence on nuclear deformation, the total internal conversion coefficient of the 121.8-kev 2+-0+ transition in ellipsoidal Sm152[over]90 was measured to be 1.135 ± 0.010 with a high accuracy coincidence-sum method. The K-shell to total internal conversion ratio was determined to be 0.588 ± 0.003 with a [beta] spectrometer...The experiment revealed no deviation from theory nor indications of strong dependence on nuclear deformation; it therefore did not confirm recent beliefs in this regard. The details of the coincidence-sum method were described. The K electron to total electron capture ratio, from Eu152 to the 1.53 Mev state in Sm152 was also measured to be 0.79±0.02."
Date: July 17, 1961
Creator: Lu, D. C. & Schupp, G.
System: The UNT Digital Library
Current-Switching Circuitry (open access)

Current-Switching Circuitry

This paper discusses a group of high-speed switching circuits using the basic current-switching mode of operation. The first part of the paper presents a dynamic analysis of the basic current-switching mode and the second part is the dynamic and steady-state analysis of a current-switching flip-flop.
Date: July 17, 1961
Creator: Salvador, Jack Gilbert & Pederson, D. O.
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Semiannual Progress Report for Period Ending April 30, 1961 (open access)

Aircraft Nuclear Propulsion Project Semiannual Progress Report for Period Ending April 30, 1961

This report includes a summary of materials research and engineering of the aircraft nuclear propulsion project.
Date: July 17, 1961
Creator: unknown
System: The UNT Digital Library