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40-MW(e) Prototype High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending June 30, 1962

Description: Research and development progress specifically directed toward the construction of a 40-Mw(e) prototype power plant employing a high-temperature, gas-cooled, graphitemoderated reactor known as the HTGR is reported. Irradiation of element III-B in the in-pile loop continued satisfactorily. The element has generated a total of l36.3 Mw-hr of fission heat. The gross activity in the purge stream increased slightly to about 350 mu C/cm/sup 3/. By taking larger gas samples than were previously taken,… more
Date: October 31, 1963
Item Type: Refine your search to only Report
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40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959

Description: The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading… more
Date: September 1, 1960
Item Type: Refine your search to only Report
open access

75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY

Description: For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date: January 1, 1960
Creator: Gronemeyer, F.C. & Merryman, J.W.
Item Type: Refine your search to only Report
open access

80" Bubble Chamber Expansion System Preliminary Operating Procedures

Description: These procedures are intended to be used for the initial operation of the expansion system and serve as a basis for a more complete and revised form to be written once operating experience has been gained. An attempt has been made to offer a logical and systematic presentation to facilitate operation and maintenance of the system by the operating personnel. Thus, the sequence of valve actuations has been presented in matrix and check list form to minimize errors; this also has the advantage of … more
Date: January 7, 1964
Creator: Goodzeit, C. L.
Item Type: Refine your search to only Report
open access

80" Bubble Chamber Expansion System Summary of Piston Motion Studies

Description: Prior to assembly into the 80" bubble chamber, the expansion system was subjected to a series of tests to check piston dynamics and gain information on the reliability of the various components. Furthermore, the rest provided operating personnel with the opportunity to become familiar with the operation and maintenance of the expansion system. Two separate tests were performed with the apparatus that was located at the north end of the AGS experimental area; one during the week of Oct. 15 and t… more
Date: January 7, 1964
Creator: Goodzeit, C. L.
Item Type: Refine your search to only Report
open access

80" Chamber - Low Energy Beams

Description: One of the major, as well as first, decisions which must be taken on a large chamber is to decide on the direction of the magnetic field, i.e., vertical or horizontal. Either alternative has advantages and disadvantages ad it is the intention of this note to discuss these features.
Date: January 3, 1964
Creator: Rau, R. R.
Item Type: Refine your search to only Report
open access

100-C water plant

Description: System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reac… more
Date: February 20, 1961
Creator: Agar, J. D.
Item Type: Refine your search to only Report
open access

100-K Area electrical power system load and voltage study for project CG-775. Revision

Description: The proposed increased water capacity for 100-K plants will increase the electrical load to be supplied. The load study showed that the capacity of the existing 13.8 kV system is adequate to carry the increased loads proposed for Project CG-775, while for the 5 kV system, an expanded power system is proposed. Likewise, the voltage regulation on the kV system bus will be excessive, and voltage regulators should be added.
Date: February 22, 1960
Creator: Thorson, W. R.
Item Type: Refine your search to only Report
open access

100-N Decontamination Facility Design Guide.

Description: Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date: March 8, 1960
Creator: Bainard, W. D.
Item Type: Refine your search to only Report
open access

100-N technical manual. Volume 2A: Systems descriptions

Description: This report contains engineering drawings for the control room, reactor monitoring systems, and reactor control systems for the N reactor. Each console in the control room is detailed. Other systems discussed are: stack air monitoring system, charging machine control systems, and heating and ventilation control systems. A N reactor plant glossary is included.
Date: December 31, 1963
Item Type: Refine your search to only Report
open access

100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report

Description: A thermoelectric generator which produces 100 watts of electrical power continuously over a six-month operational life in a space environment was designed. It employs the heat produced by the decay of Cm/sup 24/ as the source of power. Uniform output over the operational life of the generator is accomplished by means of a thermally actuated shutter which maintains the hot junction temperature of the thermoelectric conventer at a constunt figure by varying the amount of surplus heat which is rad… more
Date: May 1, 1960
Creator: Weddell, J. B. & Bloom, J.
Item Type: Refine your search to only Report
open access

105-F intermediate range test hole parameters

Description: This report discusses 105 intermediate range test hole which was bored in 105-F to demonstrate reactor hole boring techniques. This test hole was then utilized to determine the performance of neutron sensitive gamma compensated ion chambers (CIC), the effectiveness of epoxy reactor shield plug designs, the compatability of the prototype.components intermediate range instrumentation, and demonstrate the performance of an intermediate range monitor system on a typical Hanford reactor application.… more
Date: November 16, 1964
Creator: Erickson, G. L.
Item Type: Refine your search to only Report
open access

190-DR steam turbine backup adequacy report

Description: Because of the questionable performance of the 190-DR steam backup system during the power outage of April 6, 1962, it is felt that a general review of the DR secondary water system capabilities and the standby status of the pumping units is warranted. This report shall briefly describe the performance of the steam backup system during the April 6 power outage and the subsequent power outage of July 10, 1962. Since the former outage, tests have been conducted on the steam pump units to determin… more
Date: November 8, 1962
Creator: Radtke, W. H. & Keplinger, E. R.
Item Type: Refine your search to only Report
open access

190-H drawdown test

Description: A discrepancy of about 1000 gpm has existed between the full-flow recorded 190, 105 and ROL flows. While past operating practices have not used the 190 or ROL flow rates for official purposes, the disquieting, though not theoretically unexplicable, differences require some quantitative resolution. On November 24, 1962, a drawdown test of the 190-H storage tanks was performed to establish the accuracy of the various flowmeters. The drawdown test of the 190 storage tanks was run at the beginning … more
Date: January 17, 1963
Creator: Cremer, B. R. & Bokish, K. P.
Item Type: Refine your search to only Report
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