Contraction rates of H and K reactors (open access)

Contraction rates of H and K reactors

It was found from graphite irradiations that the changes can be described by a growth component and a contraction component, and that the contraction is a linear function of exposure, while the growth is a function of both exposure and temperature which saturated at high exposures, say 3000 MWD/a ton. A graph is included. Contraction rate is determined for KW, KE, and H piles.
Date: February 4, 1959
Creator: Richey, C. R.
System: The UNT Digital Library
CORE LEVITATION IN THE EGCR IN CASE OF MAIN COOLANT PIPE FAILURE (open access)

CORE LEVITATION IN THE EGCR IN CASE OF MAIN COOLANT PIPE FAILURE

Results of an analysis to determine the extent of displacement of the EGCR core due to blowdown in case of several postulated hot main gas coolant pipe failures are summarized. Results show that the core will be damaged for ary hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing prior to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect. (auth)
Date: August 4, 1959
Creator: Fontana, M.H.
System: The UNT Digital Library
Existing reactor expansion study basis (open access)

Existing reactor expansion study basis

The latest HAPO Five Year Program review, indicates that significant increases in Pu production from the eight existing Hanford reactors may be achieved. These production increases would be attained by a combination of several methods including increased process water flow rates, reactor coolant outlet temperature, improved time operated efficiency, conversion ratio and induced transient reactivity looses. In order to provide a realistic basis for budgeting to meet these or other increased production goals, it to necessary that a study program be undertaken to determine in general terms the more nearly optimum plant changes required and to evaluate the economic and technical feasibility of achieving future process conditions. The purpose of this document is to present a plan for the execution of the prepared study. Included in the study outline are the basis study consideration, problem assignments and schedules, required manpower estimates, and tentative cost estimates.
Date: June 4, 1959
Creator: Heacock, H. W.
System: The UNT Digital Library
Scope report, discharge area remote manipulator (open access)

Scope report, discharge area remote manipulator

Trends in reactor operation and maintenance have created the need for a rear face Hanford reactor manipulator which can routinely perform certain maintenance and operational functions, and which under high radiation exposure conditions can permit ruptured slug removal or other emergency type operations tb be conducted with little or no personnel radiation exposure. Because of the need for several tools, it was decided that the most desirable approach to a satisfactory manipulator program would be to provide a multi-tool manipulator which could do several distinct tasks. Of these tasks removing the rear face nozzle caps to facilitate removal of ruptured slugs and performance of ruptured slug removal operation were the most profitable routine functions which could be accomplished by a manipulator. The conventional mechanical arm was considered for use in non-routine situations such as recovery of slugs lodged in rear face piping or other disaster type situations which on occasions do happen. To insure the quickest return on the economic benefits of the program, the cap remover development was conducted as a separate study since it is more definitive then,the remainder of the manipulator program. A second phase involving the application of the mechanical arm and development of specialized tools …
Date: March 4, 1959
Creator: Frantz, C. E.
System: The UNT Digital Library
Solidification of high level wastes Part 1, Evaporation and calcination of Purex IWW--volatility and leachability of fission products (open access)

Solidification of high level wastes Part 1, Evaporation and calcination of Purex IWW--volatility and leachability of fission products

The basic objective of the storage of radioactive wastes is to protect humanity from: (1) direct radiation, (2) contamination of food and water supplies, and (3) contamination of mineral resources. There have been many proposals for the disposal of high level liquid wastes from chemical plants processing nuclear fuels. These include our present Hanford system of tank storage; disposal to deep wells, such as the oil industry uses for discard of brines they pump; storage in salt caverns; disposal to selected geological formations, such as salt domes and anticlines, or impermeable substances, such as clay, etc.; or release to the depths of the ocean. Only the use of tanks and salt caverns can be considered as storage systems. The latter is essentially a dry mine into which material would be placed as solids or packaged liquids. There is no control over the movement of activity with the other disposal methods. This is also potentially true for tank storage should corrosion or other damage cause leakage. Storage of highly radioactive wastes pose a problem in handling the heat generated by fission product decay. Thus, it is advantageous to look for a substance of high density and high thermal conductivity to help …
Date: August 4, 1959
Creator: Barton, G. B.
System: The UNT Digital Library