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100 Areas water treatment specifications

Description: This memorandum discussed review of the data from tests using alum in the treatment of pile process water, and using activated silica as a coagulant aid during period of low water temperature, which shows that this method should be substituted for the present method of treating pile process water in all 100 Areas. It was recommended that the water treatment procedures and specifications attached to this memorandum be initiated as standard practice in all 100 Areas as soon as it is possible to m… more
Date: July 11, 1952
Creator: Greninger, A. B.
Item Type: Refine your search to only Report
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100-B Area flow analysis

Description: Results of experimental programs indicate that it might be desirable in the future to modify the existing reactors by replacing the aluminum process tubes with tubes made of a zirconium alloy. The zirconium tubes would be more corrosion resistant than the aluminum ones and would also be stronger at higher temperatures. These new tubes would have the same outer diameter as the present tubes (for ease of handling and in order to provide adequate graphite cooling) but would have a thinner wall (si… more
Date: June 1, 1957
Creator: Bainard, W. D.
Item Type: Refine your search to only Report
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100-K water plant facilities data for G.E. scoping

Description: This report discusses seven items related to the design of the 100-K water plant facilities. These items include: the number of process water connections to the reactor building, valving at the control building, and number of main pumping units; effect on heating system of the Hanford power outage during the winter period; reactor supply conditions; power requirements and steam flow at the local power plant; the service water system; general arrangement of the heat exchanger building; and pumpi… more
Date: August 8, 1952
Creator: Patterson, R. K.
Item Type: Refine your search to only Report
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100-Mw Nuclear Power Plant Utilizing a Sodium Cooled, Graphite Moderated Reactor

Description: The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel ha… more
Date: February 28, 1958
Item Type: Refine your search to only Report
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100-N temporary construction line considerations

Description: Present thinking and planning appears to be developing from the following factors as concern the 13.8 KV temporary construction power limit. 1. It is understood that the present intent is to supply 100-N operating requirements from a single stub source in the 230 KV loop. 2. The original thoughts were to obtain construction power over a 13.8 KV line from 151-D substation. 3. Construction load requirements are now less than originally planned since steam has been substituted for electrical drive… more
Date: December 30, 1958
Creator: Mollerus, F. J.
Item Type: Refine your search to only Report
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105-N charge-discharge rates

Description: Figures have and can be generated that indicate a higher charge-discharge rate if required before 105-N will be comparable with existing reactors. Also, these figures show an apparent operating cost incentive to increase the charge-discharge rates proposed for 105-N. Although these figures may be true by themselves, other figures developed from the same information and stated on a basis that affords a true comparison, show that the proposed rates for 105-N are compatible with those in existing … more
Date: July 2, 1959
Creator: Nesbitt, J. F.
Item Type: Refine your search to only Report
open access

183 B-C cross tie justification and scope

Description: After the present solid slugs are replaced with the new I&E elements` in the 105-B reactor, the friction loss for the reactor cooling water will be decreased with a resulting opportunity for increase in flow through the reactor. The amount that this flow could be increased is limited by the capacity of the B water plant as well as the reactor itself. It is possible that there will be a shortage of filtered water at 183-B during the critical periods of each year. To overcome this possible shorta… more
Date: December 2, 1957
Creator: Brinkman, L. B.
Item Type: Refine your search to only Report
open access

190-C pump capacity

Description: The purpose of this document is to update 190-C pump capacity information previous released in HW-52449{sup 1} and HW-58580{sup 2}. Improvements in motor cooling has resulted in raising the previous 3500 HP limit to 3660 HP{sup 3} thus increasing total pumping capacity.
Date: June 22, 1959
Creator: Watson, D. F.
Item Type: Refine your search to only Report
open access

200 Area processing rates

Description: Two types of ``feedstock,`` i.e. irradiated uranium and uranium from underground storage, are processed by the 200 Areas. Future operations may add irradiated thorium as a supplementary feed material. In either case, the major portion of future feedstocks is presumed to be in the form of irradiated metal, i.e. uranium and/or thorium, resulting in an almost complete dependence of the required 200 Area processing rate on reactor power levels and metal irradiation history. This document presents c… more
Date: April 12, 1955
Creator: Platt, A. M.
Item Type: Refine your search to only Report
open access

200 Area waste storage study

Description: As a part of the five year budget study requested by HOO-AEC, a study of separations waste storage requirements for this period was made. This study took into consideration the variant estimates of amount of irradiated uranium to be processed, and the goals in the waste reduction research and development program. The conclusions of this study were at variance, to some extent, with prior studies. Interest has been expressed in publication of this study to permit independent assessment of its bas… more
Date: March 27, 1956
Creator: Hanthorn, H.E.
Item Type: Refine your search to only Report
open access

200 area weekly report

Description: This is the weekly progress report for the 200 area for the week of November 10, 1955. Areas discussed pertaining to the solvent extraction plants include operation status, 232-F Building, 221-F - NFE dissolver, 200-F - solvent purification, 221-F - increased throughput, 241-F additional waste storage tanks, 221-F canyon pumps.
Date: November 10, 1955
Item Type: Refine your search to only Report
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