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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

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

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

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

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

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

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

Acoustic detection of the collapse of a sodium vapor bubble in an infinite sea of sodium

Description: A discussion of the problem of sodium vapor bubble collapse is presented. The physics of vapor collapse is presented in light of the work by Peppler et al. Theoretical estimates of the sound source level based on the work by Rayleigh and Judd are compared to an approximate pressure-volume work approach and recent experimental observations. Reactor ambient noise and transmission loss considerations are presented in regard to their impact on this detection problem. A methodology is proposed which considers the importance of the sound source level, ambient noise, transmission loss and a detection threshold and provides a means by which the feasibility of sodium vapor bubble collapse detection in an operating LMFBR may be assessed. The interrelationships between the detection threshold and the probability of detection and false alarm are discussed and applied to a standard acoustic square law detection system. This analysis clearly illustrates that the feasibility of such a detection system is strongly dependent on the knowledge of sound source levels, ambient noise levels and the transmission loss between the source and receiver. Furthermore, requirements of a high degree of probability of detection and a low probability of false alarm were found to require a high signal to noise ratio for a single sensor system but that the probability of false alarm requirement could be relaxed for systems multiple independent sensors. Finally, the need for additional experimental and theoretical information is presented in terms of sound source levels, ambient noise and a means for determining transmission loss. (auth)
Date: December 1, 1975
Creator: Carey, W. M.
Partner: UNT Libraries Government Documents Department

Flow-induced vibration in LMFBR steam generators: a state-of-the-art review

Description: This state-of-the-art review identifies and discusses existing methods of flow-induced vibration analysis applicable to steam generators, their limitations, and base-technology needs. Also included are discussions of five different LMFBR steam-generator configurations and important design considerations, failure experiences, possible flow-induced excitation mechanisms, vibration testing, and available methods of vibration analysis. The objectives are to aid LMFBR steam-generator designers in making the best possible evaluation of potential vibration in steam-generator internals, and to provide the basis for development of design guidelines to avoid detrimental flow-induced vibration. (auth)
Date: May 1, 1975
Creator: Shin, Y.S. & Wambsganss, M.W.
Partner: UNT Libraries Government Documents Department

Some findings from FFTF piping and component design analyses

Description: A number of questions that have been commonly raised during elevated temperature design of FFTF components and pipelines are identified and discussed. Although the questions do not lend themselves to simple answers, some guidance based on analysis findings is given. Based upon the limited data developed, uniaxial stress relaxation data can give a reasonable pattern of structural creep damage as a function of time. However, the creep damage magnitude may be as much as a factor of two too low. Other geometries and/or loading may show much larger variations between the uniaxial and complex hardware creep damage response. (auth)
Date: September 1, 1975
Creator: Severud, L.K.; Weiner, E.O. & Winkel, B.V.
Partner: UNT Libraries Government Documents Department