Preservation of Laboratory Instruments in Static Storage (open access)

Preservation of Laboratory Instruments in Static Storage

It is desirable to place laboratory instruments in static storage so that they may be put into operation with only normal servicing. Such instruments may be subject to many forms of deterioration. There may be deterioration of metal parts due to chemical and electrolytic corrosion and the effects of moisture, excessive dryness, and microorganisms, i.e., mildew on organic parts. To preserve such instruments without disassembly or troublesome surface coatings, requires methods that will remove the major cause of deterioration - that is, excessive humidity, by reducing and maintaining the relative humidity of the air surrounding the item at 30 per cent or less. It is also necessary to eliminate or separate hygroscopic materials from the item since they will cause corrosion, by surface adsorption and condensation, even though a dry atmosphere is maintained. The methods and materials used must not only be efficient and economical but also require a minimun of maintenance, Protection against physical damage and temperature extremes is dependent upon the storage site and is not considered in this report.
Date: February 22, 1950
Creator: Gregg, J. L. & Shackelford, M. A.
System: The UNT Digital Library
STUDIES OF MIXING IN THE LOWER PLENUM OF A QUARTER-SCALE FLOW MODEL OF THE PWR REACTOR (open access)

STUDIES OF MIXING IN THE LOWER PLENUM OF A QUARTER-SCALE FLOW MODEL OF THE PWR REACTOR

None
Date: February 22, 1957
Creator: Hazard, H.R. & Rotkowitz, A.
System: The UNT Digital Library
A COMPARISON OF THE EFFECTS OF OXIDATION AND THE EFFECTS OF NEUTRON IRRADIATION ON GRAPHITE (open access)

A COMPARISON OF THE EFFECTS OF OXIDATION AND THE EFFECTS OF NEUTRON IRRADIATION ON GRAPHITE

None
Date: February 22, 1952
Creator: Hennig, G.
System: The UNT Digital Library
The Physics of the Fused-Salt Reactor Experiment (open access)

The Physics of the Fused-Salt Reactor Experiment

In 1954 the Oak Ridge Nationai Laboratory operated, for demonstration purposes, a high-temperature circulatingfuel reactor, employing as fuel enriched uranium fluoride dissolved in molten fluorides of other cations. A BeO moderator was used. At a maximum power of 2.5 Mw, 100 Mw hr were obtained. A negative temperature coefficient resulting largely from fuel expansion yielded exceptional stability of the reactor, and made the reactor a slave of the power demand. Xe/ sup 135/ and some of the other fission fragments are not retained in the fuel; hence, there is no xenon poisoning and relatively little danger of spreading of gaseous fission fragments in case of an accident. The advantages of liquid-fuel reactors (elimination of radiation dnmage and thermal stresses in solid fuel elements, ease of fabrication and fuel reprocessing) are combined with low pressures at very high temperatures. (auth)
Date: February 22, 1957
Creator: Ergen, W.K.
System: The UNT Digital Library
Increased process water pressure to 105 buildings (open access)

Increased process water pressure to 105 buildings

This document discusses increases in water pressure from the 190 Building process pumps which has been contemplated for a range of pressures up to 550 PSIG. The existing process pumps are dual units, consisting of a steam turbine driven primary pump operated: in series with an electric driven secondary pump. The secondary pumps installed in 100-B, D, F, and H Areas were designed for 400 PSIG working pressure, and were given factory hydrostatic tests of 600 PSIG. The 100-DR pumps were given factory hydrostatic tests of 650 PSIG. The Ingersoll-Rand Company advises that a working pressure of 425 PSIG is as high as they would-recommend for pump casing pressure on the secondary pumps. In consideration of problems incident to increased operating pressures, the immediate limiting factor is the total head pressure permissible on secondary pump casings. Other limiting factors are filter plant capacities, and 183 process water capacities.
Date: February 22, 1951
Creator: Measly, H. F.
System: The UNT Digital Library
[Discussion by R. M. Evans at a meeting held with the members of the Military Liaison Committee on February 17, 1954] (open access)

[Discussion by R. M. Evans at a meeting held with the members of the Military Liaison Committee on February 17, 1954]

Characteristics of the heavy water moderated and cooled reactor when fueled with natural uranium were compared with those of Hanford. The following topics were covered: (1) fundamental safety of the Savannah River Plant reactor and its fundamental efficiency as neutron collector; (2) many critical volumes result in a complex control system and high sensitivity of flux pattern to rod position changes; (3) due to lack of time had to sue slugs initially; (4) had to use D{sub 2}O sparingly; (5) effects of circulating cooling system; and (6) heat transfer considerations. Topics also discussed were Savannah River reactor with enriched loadings and irradiation of thorium in lieu of lithium alloy.
Date: February 22, 1954
Creator: unknown
System: The UNT Digital Library