Resource Type

States

Nuclear Safety Program Semiannual Progress Report for Period Ending June 30, 1962 (open access)

Nuclear Safety Program Semiannual Progress Report for Period Ending June 30, 1962

Progress in nuclear safety research and development is reported. Topics covered include: reactivity effects of fuel displacements in a pool-type reactor, release of fission products on out-of-pile melting of reactor fuels, release of fission products on in-pile melting of reactor fuels, fission product transport evaluations, characterization and control of accident-released fission products, nuclear safety pilot plant, preparation of reactor containment hardbook, and radiochemical plant safety studies. (M.C.G.)
Date: August 24, 1962
Creator: unknown
System: The UNT Digital Library
Electron microprobe analysis of irradiated S8ER cladding (open access)

Electron microprobe analysis of irradiated S8ER cladding

Extensive precipitation was observed in S8ER cladding following irradiation. Electron microprobe analysis was proposed as a means to identify these precipitates. Subsequently, the electron microprobe was successfully used for qualitative analysis of unirradiated and irradiated S8ER cladding. The unirradiated, thermally aged control specimen analyzed showed two major precipitates. One, a randomly distributed intergranular phase, contained Ti, Mo, Fe, Cr and Ni and a second, a randomly distributed intragranular phase, contained Si, Mo, Fe, Cr and Ni. The irradiated specimen analyzed showed the same precipitates. The phase containing Ti, Mo, Fe, Cr and Ni was also randomly distributed intergranularly. The phase containing Si, Mo, Fe, Cr and Ni was in the grain boundaries, and preferentially segregated to the outer and inner diameter.
Date: August 24, 1967
Creator: Krupp, W.E. & Cooper, L.
System: The UNT Digital Library
Hazards review Phase 1 fission product processing in B-plant (open access)

Hazards review Phase 1 fission product processing in B-plant

Future operation of B-Plant for Phase I fission product processing involves may of the hazards associated with current chemical Processing Department activities in both the Purex and Redox Plants. The specific B-Plant hazards under Phase I operations are discussed in this report from the standpoint of comparable Purex and Redox hazards.
Date: August 24, 1961
Creator: Michels, L. R. & Zahn, L. L.
System: The UNT Digital Library
A feasibility study: The application of cooling towers for reduction of Hanford Plant heat load to the Columbia River (open access)

A feasibility study: The application of cooling towers for reduction of Hanford Plant heat load to the Columbia River

Hanford production reactor operation requires the rejection of very large heat loads. At the present time the heat load is rejected to the Columbia River by the reactor effluent. At low river flows the hot effluent can have appreciable effects on river temperatures. The purpose of this study is to evaluate the feasibility and costs of Cooling Towers as a means of reducing the heat load rejected to the Columbia River. After evaluation of published information, available data, and Hanford plant conditions, it is concluded that: (1) That an induced draft cooling tower, because of its longer cooling range,, would be an effective cooling device for reduction of gross heat load rejected to the Columbia River. Additional study will be required to determine effective use on an area to area basis. (2) That a basically wood, counter-flow, induced draft cooling tower could be installed for approximately $1600 to $2000 per megawatt capacity. This cost is a probable minimum and might be increased by the cost of auxiliary features required for radiation control. (3) That additional study and developmental testing would be required to determine the extent of contamination problems which would result from the cooling tower installation. These problems would …
Date: August 24, 1962
Creator: Peck, G. E.
System: The UNT Digital Library
Production Test IP-708, Oil-quenched hot-die-sized element evaluation (open access)

Production Test IP-708, Oil-quenched hot-die-sized element evaluation

The objective of this test is to evaluate the effects of oil quenching, alpha annealing, and an Al-Si braze pre-canning treatment on the irradiation behavior of hot-die-sized fuel elements.
Date: August 24, 1964
Creator: Hladek, K. L.
System: The UNT Digital Library
An Analysis of the Inherent Stability of the EOCR (open access)

An Analysis of the Inherent Stability of the EOCR

The inherent stability of the EOCR at full power, exclusive of the heat exchanger, is investigated. Space and time dependent differential equations and transfer functions for the nuclear and thermal processes occurring in the reactor core and vessel are derived. Reactor stability is analyzed by application of the Nyquist stability criterion. The results show that the EOCR has an extremely large margin of inherent stability. (auth)
Date: August 24, 1962
Creator: Gossmann, S.R.
System: The UNT Digital Library
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JULY 1965 (open access)

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JULY 1965

None
Date: August 24, 1965
Creator: unknown
System: The UNT Digital Library
SNAP reactor control-drum drive (open access)

SNAP reactor control-drum drive

None
Date: August 24, 1964
Creator: Kellogg, L. G.
System: The UNT Digital Library
Recrystallization of Beta-Heat-Treated Dingot-Uranium Cores. Topical Report (open access)

Recrystallization of Beta-Heat-Treated Dingot-Uranium Cores. Topical Report

Annealing beta-heat-treated production-size dingoturanium core blanks in the high alpha range (1150 to 1200 deg F) produced a fine, equiaxed grain size by a recrystallization process. The extent of recrystallization is dependent upon the rate of cooling through the beta-to-alpha transformation, the time and temperature of annealing, and whether or not impurities that retard grain growth are present. The cooling rate through the beta-to-alpha transformation was varied by using a range of beta temperatures and air cooling times prior to quenching into water. Longer air cooling times are permissible at the higher beta temperatures; however, the greatest amount of induced lattice strain was obtained after an air delay of only 2 seconds before quenching. Decreasing the annealing temperature results in a corresponding increase in the annealing time required for an equivalent amount of recrystallization. A second phase, present in the alloyed dingot metal, inhibited recrystallization and grain growth. Alloyed metal recrystallized progressively from the outer periphery to the center of the core, whereas unalloyed metal subjected to identical annealing conditions exhibited recrystallized grains throughout the cross section. A reduction in grain size from 0.38 mm to 0.25 mm occurred in a beta-treated, unalloyed core after annealing at 1200 deg F …
Date: August 24, 1962
Creator: Guyer, R. R. & Neumann, N .F.
System: The UNT Digital Library
Properties of Plutonium Dioxide (open access)

Properties of Plutonium Dioxide

None
Date: August 24, 1965
Creator: Moseley, J. D. & Wing, R. O.
System: The UNT Digital Library
The Discharge Petition in the House of Representatives: Background and Statistics (open access)

The Discharge Petition in the House of Representatives: Background and Statistics

This report provides a history of the use of discharge petitions in the House of Representatives, and outlines their purpose.
Date: August 24, 1967
Creator: Government and General Research Division
System: The UNT Digital Library
Operation Roller Coaster. Project Officers Report - Project 5.2/5.3b. Radiobiological, Radiochemical, and Physiochemical Analyses (open access)
Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962 (open access)

Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962

Report that describes the research and developments of the Nuclear Safety Research and Development Program of the Oak Ridge National Laboratory.
Date: August 24, 1962
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
General parameter study of a bare, cylindrical reactor having the same materials as Tory II-C (open access)

General parameter study of a bare, cylindrical reactor having the same materials as Tory II-C

This memorandum describes studies undertaken to investigate the properties of Tory II-C with the aims of reducing weight and size and in increasing performance. Space and weight limitations aboard existing sea-going launch vehicles required this general parameter study which utilizes a bare, cylindrical reactor having the same materials as Tory II-C.
Date: August 24, 1962
Creator: Stubbs, T.
System: The UNT Digital Library
Imperial Sugar Company Sugar Stock and Sales Report: August 24, 1965 (open access)

Imperial Sugar Company Sugar Stock and Sales Report: August 24, 1965

Report for Imperial Sugar Company documenting existing warehouse sugar stocks as well as a list of sugar sales for the date showing the amounts and estimated balance separated by location, raw sugar, and refined sugar sales.
Date: August 24, 1965
Creator: Imperial Sugar Company
System: The Portal to Texas History
[Imperial Sugar Company Sugar Stock and Sales Report: August 24, 1960] (open access)

[Imperial Sugar Company Sugar Stock and Sales Report: August 24, 1960]

Sugar Stock and Sales report for Imperial Sugar Company including a list of sugar sales for the date showing the amounts and estimated balance separated by location, raw sugar, and refined sugar sales.
Date: August 24, 1960
Creator: Imperial Sugar Company
System: The Portal to Texas History
[Imperial Sugar Company Estimated Daily Cash Balance: August 24, 1960] (open access)

[Imperial Sugar Company Estimated Daily Cash Balance: August 24, 1960]

Daily cash report for Imperial Sugar Company including a list of large withdrawals for the months surrounding the date showing the daily expenses and estimated balance for each entry. It also lists scheduled payments for bank loans.
Date: August 24, 1960
Creator: Imperial Sugar Company
System: The Portal to Texas History