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GCRE Critical-Assembly Studies

Description: This report follows critical-assembly studies made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiments.
Date: September 10, 1958
Creator: Dingee, David A.; Ballowe, William C.; Klingensmith, Raymond W.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
Partner: UNT Libraries Government Documents Department

Further Studies with the GCRE Critical-Assembly

Description: This report follows ciritical-assembly studies on: the effect on reactivity caused by changes in axial reflector materials; the effect on reactivity and the power perturbation caused by fast safety control-blade guides; the effect of changes in fuel-element material composition; the effect of changes in fuel-elements spacing designed to produce uniform radial power-generation rates.
Date: December 29, 1958
Creator: Dingee, David A.; Ballowe, William C.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
Partner: UNT Libraries Government Documents Department

Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

Description: From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
Partner: UNT Libraries Government Documents Department

The ML-1 Design Report

Description: From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date: May 16, 1960
Creator: Linenberger, G. A.
Partner: UNT Libraries Government Documents Department

APPR-1 Research and Development Program. Design Analysis for Flow and Temperature Measurement Program, Task No. 5

Description: From objectives: "To establish, by literature search, analysis and design, the engineering and fabrication requirements for modifying reactor components and developing and installing the necessary instrumentation to carry out a fuel temperature and flow measurement experimental program."
Date: September 26, 1958
Partner: UNT Libraries Government Documents Department

Indexes to Nuclear Regulatory Commission issuances, July--December 1995

Description: Digests and indexes for issuances of the NRC, the Atomic Safety and Licensing Board, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: (1) case name, (2) full text reference, (3) issuance number, (4) issued raised by appellants, (5) legal citations, (6) name of facility and Docket number, (7) subject matter, (8) type of hearing, and (9) type of issuance.
Date: April 1, 1996
Partner: UNT Libraries Government Documents Department

A Methodology for Evaluation of Inservice Test Intervals for Pumps and Motor Operated Valves

Description: The nuclear industry has begun efforts to reevaluate inservice tests (ISTs) for key components such as pumps and valves. At issue are two important questions--What kinds of tests provide the most meaningful information about component health, and what periodic test intervals are appropriate? In the past, requirements for component testing were prescribed by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The tests and test intervals specified in the Code were generic in nature and test intervals were relatively short. Operating experience has shown, however, that performance and safety improvements and cost savings could be realized by tailoring IST programs to similar components with comparable safety importance and service conditions. In many cases, test intervals may be lengthened, resulting in cost savings for utilities and their customers.
Date: August 1, 1999
Creator: McElhaney, K.L.
Partner: UNT Libraries Government Documents Department

Regulatory and Technical Reports (Abstract Index Journal). Annual compilation for 1995, Volume 20, No. 4

Description: The Nuclear Regulatory Commission`s annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1994) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.
Date: April 1, 1995
Creator: Sheehan, M.
Partner: UNT Libraries Government Documents Department

Shallow Flaws Under Biaxial Loading Conditions, Part II: Application of a Weibull Stress Analysis of the Cruciform Bend Specimen Using a Hydrostatic Stress Criterion

Description: Cruciform beam fracture mechanics specimensl have been developed in the Heavy Section Steel Technology (HSST) Program at Oak Ridge National Laboratory (ORNL) to introduce a prototypic, far- field, out-of-plane biaxird bending stress component in the test section that approximates the nonlinear biaxial stresses resulting from pressurized-thernxd-shock or pressure-temperature loading of a nuclear reactor pressure vessel (RPV). Matrices of cruciform beam tests were developed to investigate and quantify the effects of temperature, biaxial loading, and specimen size on fracture initiation toughness of two-dimensional (constant depth), shtdlow, surface flaws. Tests were conducted under biaxial load ratios ranging from uniaxial to equibiaxial. These tests demonstrated that biaxial loading can have a pronounced effect on shallow-flaw fracture toughness in the lower transition temperature region for RPV materials. Two and three- parameter Weibull models have been calibrated using a new scheme (developed at the University of Illinois) that maps toughness data from test specimens with distinctly different levels of crack-tip constraint to a small scale yielding (SSY) Weibull stress space. These models, using the new hydrostatic stress criterion in place of the more commonly used maximum principal stress in the kernel of the OW integral definition, have been shown to correlate the experimentally observed biaxiaI effect in cruciform specimens, thereby providing a scaling mechanism between uniaxial and biaxial loading states.
Date: August 1999
Creator: Bass, B. R.; McAfee, W. J. & Williams, P. T.
Partner: UNT Libraries Government Documents Department

Compilation of data and descriptions for United States and foreign liquid metal fast breeder reactors

Description: This document is a compilation of design and engineering information pertaining to liquid metal cooled fast breeder reactors which have operated, are operating, or are currently under construction, in the United States and abroad. All data has been taken from publicly available documents, journals, and books. (auth)
Date: August 1, 1975
Creator: Appleby, E.R.
Partner: UNT Libraries Government Documents Department

Licensed operating reactors. Status summary report data as of 12-31-94: Volume 19

Description: The Nuclear Regulatory Commission`s annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1994) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.
Date: April 1, 1995
Partner: UNT Libraries Government Documents Department

Space-reactor system and subsystem investigations: cost and schedule estimates for reactor and shield subsystems technology development. SP-100 Program

Description: This report presents cost and schedule estimates of the technology development for reactor and shielding subsystems of a 100-kWe class space reactor electric system. The subsystems technology development (which includes reactor and shield subsystems ground testing) is supported by materials and processes development and component development. For the purpose of the cost estimate, seven generic types of reactor subsystems were used: uranium-zirconium hydride, NaK-cooled thermal reactor; lithium-cooled, refractory-clad fast reactor; Na- or K-cooled fast reactor; in-core thermionic reactor; inert gas-cooled particle fuel reactor; inert gas-cooled metal-clad fast reactor; and heat pipe-cooled fast reactor. Also three levels of technology were included for each of the generic types of reactor subsystem: current, improved, and advanced. The data in this report encompass all these technology levels. The shielding subsystem uses both gamma (heavy-metal) and neutron (hydrogenous material) shields. The shields considered in this report would be used in conjunction with unmanned payloads.
Date: June 30, 1983
Creator: Determan, W.R.; Harty, R.B. & Hylin, C.
Partner: UNT Libraries Government Documents Department

SP-100 low mass shield design

Description: The shielding considerations for an unmanned space reactor system are somewhat different from those for a terrestrial reactor. An unmanned operation in space implies that only a shadow shield, rather than a 4..pi.. one, is required to protect payload hardware that typically can tolerate 10/sup 4/ to 10/sup 6/ times more radiation than can a human crew. On the other hand, the system mass, of which the radiation shield can be a significant fraction, is a severe constraint for space reactors and not normally a problem with terrestrial ones. The object of this paper is to briefly summarize advancements made on various aspects of low mass shield design for space reactors, including materials and their arrangements, geometric factors and their potential impact on system design optimization, and proposed new configuration concepts for further mass reduction.
Date: January 1, 1985
Creator: Carlson, D.E.
Partner: UNT Libraries Government Documents Department

Selection of power plant elements for future space electric power systems

Description: A study on the type of nuclear reactor power plants that should be developed for future space missions is described. After careful consideration of power plant configuration weights, sizes, reliabilities, safety, development cost and time, the configuration selected to be pursued was a heat-pipe reactor design with thermoelectric converters and heat-pipe radiator.
Date: January 1, 1979
Creator: Buden, D.
Partner: UNT Libraries Government Documents Department

100-kW/sub e/ Nuclear space electric power source

Description: The current 100-kW/sub e/ space nuclear power technology program could provide an electric power source for nuclear electric propulsion. The power plant is relatively compact, light weight, and has the advantages of long life and immunity to degradation while passing through the Van Allen belts. The reactor is a unique design using heat pipes to transfer heat from the reactor core to the thermoelectric converters. The converters are an improved design over those used in the radioisotope space program. The radiator, used to eliminate waste heat to space, also makes use of heat pipes. All single failure points have been eliminated from the power plant design and redundancies are provided to ensure high reliability. The power plant configuration and some key results of the current component experimental program are discussed.
Date: January 1, 1979
Creator: Buden, D.
Partner: UNT Libraries Government Documents Department

Missions and planning for nuclear space power

Description: Requirements for electrical and propulsion power for space are expected to increase dramatically in the 1980s. Nuclear power is probably the only source for some deep space missions and a major competitor for many orbital missions, especially those at geosynchronous orbit. Because of the potential requirements, a technology program on reactor components has been initiated by the Department of Energy. The missions that are foreseen, the current reactor concept, and the technology program plan are described.
Date: January 1, 1979
Creator: Buden, D.
Partner: UNT Libraries Government Documents Department

Evaluation of the effects of an integral fin spacer design on predicted fuel pin and subassembly duct performance

Description: The effect of an integrally finned fuel pin cladding design on LMFBR subassembly performance has been evaluated. Effects on thermal/hydraulics, fuel pin lifetime and duct lifetime are considered. Results are presented for 19, 61 and 217 pin subassemblies.
Date: January 1, 1976
Creator: Sutherland, W.H.; Cantley, D.A.; McCurry, D.C. & Parker, M.B.
Partner: UNT Libraries Government Documents Department

LMFBR spent fuel and new fuel inspection and handling

Description: If the hot cells used for inspection and preparation of liquid metal fast breeder reactor fuel assemblies can be located so that the fuel assemblies can be moved directly to and from the sodium filled decay storage tank, the fuel handling problems can be simplified and a fuel handling machine may be eliminated. The hot cells can also serve as a transfer lock through the outer containment barrier, thereby permitting uninterrupted reactor operation during fuel transfer to and from the decay storage tank. 5 references (auth)
Date: January 1, 1975
Creator: Youngquist, C.H.
Partner: UNT Libraries Government Documents Department