Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE (open access)

Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE

Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
Date: June 1, 1960
Creator: Ballif, J. L.; Hayward, B. R. & Walter, J. W.
System: The UNT Digital Library
OMR (Piqua) Unitized Control-Safety Rod Prototype Tests (open access)

OMR (Piqua) Unitized Control-Safety Rod Prototype Tests

Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).
Date: June 30, 1960
Creator: Howell, J. D. & Weeks, C. C.
System: The UNT Digital Library
Operating Experience with Heat Transfer System Pumps at the Hallum Nuclear Power Facility (open access)

Operating Experience with Heat Transfer System Pumps at the Hallum Nuclear Power Facility

Introduction: It is the purpose of this report to describe the operating and maintenance experience obtained at HNPF on the sodium heat transfer pumps.
Date: June 15, 1964
Creator: Durand, R. E.
System: The UNT Digital Library
A Rotary Kiln for the Controlled Oxidation of UC (open access)

A Rotary Kiln for the Controlled Oxidation of UC

Abstract: A rotary kiln was evaluated for the controlled oxidations of UC.
Date: June 30, 1965
Creator: Strausberg, S.
System: The UNT Digital Library
SNAP 10A FSEM-3 Agena Compatibility Test (open access)

SNAP 10A FSEM-3 Agena Compatibility Test

From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.
Date: June 15, 1965
Creator: Teresa, M.
System: The UNT Digital Library
HNPF Control System Response During Transient Conditions (open access)

HNPF Control System Response During Transient Conditions

Abstract: This report documents the results of power ramps inposed on the HNPF during the month of January 1964.
Date: June 15, 1964
Creator: Shaw, P. F.
System: The UNT Digital Library
Calandria Core Weld Joint Development (open access)

Calandria Core Weld Joint Development

Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.
Date: June 30, 1965
Creator: Roberts, J. G.
System: The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964 (open access)

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964

Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: June 15, 1965
Creator: unknown
System: The UNT Digital Library
Irradiation behavior of unalloyed hypostoichiometric uranium carbide, experiment AI 3-11 and review (open access)

Irradiation behavior of unalloyed hypostoichiometric uranium carbide, experiment AI 3-11 and review

A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review
Date: June 22, 1968
Creator: Frank, J. E.; Forrester, R. E. & Buck, J. S.
System: The UNT Digital Library
Analog Models for HNPF Control and Protection Studies (open access)

Analog Models for HNPF Control and Protection Studies

Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.
Date: June 15, 1964
Creator: Dunsmore, C. L.
System: The UNT Digital Library
A Further Evaluation of the Calder Hall Type of Nuclear Power Plant (open access)

A Further Evaluation of the Calder Hall Type of Nuclear Power Plant

Abstract: This report presents the results of plant optimization studies and cost estimates of the reference design for a natural uranium, graphite moderated, gas-cooled reactor and power plant which was described in NAA-SR-1833.
Date: June 28, 1957
Creator: Banks, William F.
System: The UNT Digital Library
Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices (open access)

Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices

Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.
Date: June 30, 1963
Creator: Campbell, R. W.; Doyas, R. J.; Field, H. C.; Guderjahn, C. A.; Guenther, R. L.; Hausknecht, D. F. et al.
System: The UNT Digital Library
Chemical Development, Quarterly Progress Report, October-December 1953. (open access)

Chemical Development, Quarterly Progress Report, October-December 1953.

Introduction - The work of the Chemical Development Group has included studies on the thermal and radiation stability of organic materials suitable for reactor coolants, the thermal and radiation stability of zirconium hydride, reactor safety devices involving chemical systems, and general analytical development.
Date: June 15, 1954
Creator: Loftness, R. L.
System: The UNT Digital Library
Irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12 (open access)

Irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12

A report regarding irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
Date: June 22, 1968
Creator: Arnold, J. L.
System: The UNT Digital Library
UNICORN: a program to calculate point cross sections from resonance parameters (open access)

UNICORN: a program to calculate point cross sections from resonance parameters

A report regarding Unicorn - a program used to calculate point cross-sections from resonance parameters.
Date: June 30, 1966
Creator: Otter, J. M.
System: The UNT Digital Library