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Design and Operating Experience of the ESADA Vallecitos Experimental Superheat Reactor (EVESR)

Description: Summary: "The various design features significant to superheat are described for the 12-1/2 MW., 960 psig, 1050° F, steam-cooled, low-enriched, annular-fueled, experimental superheat reactor built by the General Electric Company at the Vallecitos Atomic Power Laboratory. Results obtained during the first six months of full-power operation, on the emergency cooling system, core thermal performance, and pressure vessel temperatures are presented and compared with predictions. Operating experience with over-all reactor system is also discussed."
Date: February 1965
Creator: Ianni, P. W.; Fritz, J. R. & Law, D. D.

Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fourth Quarterly Progress Report, January 1-March 31, 1963

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. Boric acid experiments and Humboldt Bay experiments are reported.
Date: May 13, 1963
Creator: Garelis, Edward. & Meyer, Paul.

Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 2

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.
Date: April 1, 1963
Creator: Quinn, E. P.

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 31, 1963
Creator: Leitz, F. J.

Fuel Element Experiments in SADE-VBWR Nuclear Superheat Loop

Description: Abstract: Three irradiation experiments are described which have been designed to study the behavior of fuel elements in a reactors superheated steam environment. The experiments were conducted in the Superheat Advanced Demonstration Experiment loop, Vallecitos Boiling Water Reactor. The results obtained demonstrated that 304 stainless steel fuel clad in unsatisfactory for use in nuclear super heat fuel sheath designs where plastic strain or plastic deformation is allowed to occur. The results were in agreement with those reported for a previous experiment in SADE (SH-4B) and constituted the basis for change in direction of the superheat fuel program in regard to both design and fuel sheath selection.
Date: May 1963
Creator: Spalaris, C. N.; Raymont, W. R.; Lyons, M. F.; Evans, T. F.; Boyle, R. F.; Murdock, T. B. et al.

Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2

Description: The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.
Date: April 7, 1960
Creator: Lees, E. A.; Boyle, R. F. & Spalaris, C. N.