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Design criteria for a self-actuated shutdown system to ensure limitation of core damage. [LMFBR]

Description: Safety-based functional requirements and design criteria for a self-actuated shutdown system (SASS) are derived in accordance with LOA-2 success criteria and reliability goals. The design basis transients have been defined and evaluated for the CDS Phase II design, which is a 2550 MWt mixed oxide heterogeneous core reactor. A partial set of reactor responses for selected transients is provided as a function of SASS characteristics such as reactivity worth, trip points, and insertion times.
Date: September 1, 1981
Creator: Deane, N.A. & Atcheson, D.B.
Partner: UNT Libraries Government Documents Department
open access

Fourth update of the Energy Economic Data Base (EEDB) Program. Phase IV, Final report. Volume I

Description: EEDB deals with the development of cost data for nuclear and comparison electric power plants. Its objective is to provide periodic updates of technical and cost (capital, fuel and operating and maintenance) information for use in evaluating and monitoring US civilian nuclear power programs. It contains six nuclear power plant technical models and five comparison coal-fired fossil power plant technical models. (DLC)
Date: September 1, 1981
Creator: Allen, R.E.; Brown, P.E.; Kaminski, R.S.; Smith, M.H. & Ziegler, E.J.
Partner: UNT Libraries Government Documents Department
open access

Experimental method for reactor-noise measurements of effective beta. [LMFBR]

Description: A variance-to-mean noise technique, modified to eliminate systematic errors from drifting of reactor power, has been used to infer integral values of effective beta for uranium and plutonium fueled fast reactor modk-ups. The measurement technique, including corrections for a finite detector-electrometer time response, is described together with preliminary beta measurement results.
Date: September 1, 1981
Creator: Bennett, E.F.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of fuel release rate and mechanism tests under RBCB conditions. [LMFBR]

Description: This task includes theoretical evaluation of fuel/fission product release behavior from failed LMFBR fuel elements as well as an on-going experimental investigation of the mechanism of oxide fuel dispersal into flowing liquid sodium. The primary objectives of this work are to develop a fuel source term that can be used in predictive models for primary heat transfer system contamination and to understand the separate influences of important system variables (such as flow rate, oxygen impurity le… more
Date: September 1, 1981
Creator: Adamson, M.G.
Partner: UNT Libraries Government Documents Department
open access

Flow-induced vibration for light water reactors. Progress report, October 1980-December 1980

Description: Flow-Induced Vibration for Light Water Reactors (FIV for LWRs) is a four-year program designed to improve the FIV performance of light water reactors through the development of design criteria, analytical models for predicting behavior of components, general scaling laws to improve the accuracy of reduced-scale tests, and the identification of high FIV risk areas. The program is managed by the General Electric Nuclear Power Systems Engineering Department and has three major contributors: Genera… more
Date: September 1, 1981
Creator: Torres, M.R.
Partner: UNT Libraries Government Documents Department
open access

COROPT heterogeneous flux model

Description: The PHYSICS module of COROPT calculates the power and flux distributions, power fractions, required fissile enrichment, and fuel mass balances. Sufficiently accurate data are clearly necessary for the results of the thermal hydraulic and fuel pin and assembly performance analysis to be acceptable. The smooth flux and power distribution model developed for the homogeneous core COROPT application has been shown to be accurate for homogeneous cores in the range of interest. However, this model and… more
Date: September 1, 1981
Creator: Bailey, H.S. & Alexander, C.N.
Partner: UNT Libraries Government Documents Department
open access

Outline and schedule for the HTGR-SC/C licensing plan

Description: The Licensing Plan is based on licensing a HTGR-SC/C lead plant in the near term. The plan also provides reference safety material and a basis (requirements, criteria, etc.) for licensing commercial follow-on plants. The plan is structured in two parts: program management and project management, and covers three sequences of licensing activities: pre-application, construction permit application, and operating licensing application. Major activities and a schedule of events are outlined in these… more
Date: September 1, 1981
Partner: UNT Libraries Government Documents Department
open access

Specifications for the Large Core Code Evaluation Working Group Benchmark Problem Four. [LMFBR]

Description: Benchmark studies have been carried out by the members of the Large Core Code Evaluation Working Group (LCCEWG) as part of a broad effort to systematically evaluate the important steps in the reactor design and analysis process for large fast breeder reactors. The specific objectives of the LCCEWG benchmark studies have been: to quantify the accuracy and efficiency of current neutronics methods for large cores; to identify neutronic design problems unique to large breeder reactors; to identify … more
Date: September 1, 1981
Creator: Cowan, C.L. & Protsik, R.
Partner: UNT Libraries Government Documents Department
open access

Comparative analysis of LMFBR licensing in the United States and other countries - notably France. Executive summary

Description: The safety-related design aspects and licensing experiences of LMFBR projects in other democratic countries have been studied and contrasted to those in the United States in order to understand the importance of different approaches to safety, and also to understand better the system of the United States. The regulatory systems and LMFBR programs of France and the United States are contrasted in detail, and that of West Germany is also studied. The programs of Japan and the United Kingdom recei… more
Date: September 30, 1981
Creator: Golay, M.W. & Castillo, M.
Partner: UNT Libraries Government Documents Department
open access

Guide for prioritizing power plant productivity improvement projects: handbook of availability improvement methodology

Description: As part of its program to help improve electrical power plant productivity, the Department of Energy (DOE) has developed a methodology for evaluating productivity improvement projects. This handbook presents a simplified version of this methodology called the Availability Improvement Methodology (AIM), which provides a systematic approach for prioritizing plant improvement projects. Also included in this handbook is a description of data taking requirements necessary to support the AIM methodol… more
Date: September 15, 1981
Partner: UNT Libraries Government Documents Department
open access

Review of draft HTGR-SC/C design and technology development plans

Description: GCRA has approached the initial review of the subject plans from the vantage of Utility/User interests in an HTGR-SC/C Lead Project as characterized in the HTGR-SC/C Lead Project Plan. At their current stage of development, the plans are considered to represent the early views of General Atomic Company, acting as a potential NSSS vendor, on the effort necessary to design and license an HTGR-SC/C plant. As such, these plans embody GA's perception of the level of technical development and demonst… more
Date: September 22, 1981
Partner: UNT Libraries Government Documents Department
open access

MIDAS documentation

Description: MIDAS, the Master Information and Data Acquisition System, is a computerized system being implemented on FFTF to control the work released to the plant. The purpose of this system is to demonstrate the safety enhancement provided for LMFBRs when the operator has instant recall to the status of all work released to the plant, the interrelationships between functional equipment groups in the plant, and the relationships of equipment to safety functions.
Date: September 1, 1981
Creator: Seeman, S.E.
Partner: UNT Libraries Government Documents Department
open access

Experiment and analysis of instability of tube rows subject to liquid crossflow. [LMFBR]

Description: A tube array subjected to crossflow may become unstable by either one or both of the two basic mechanisms: velocity mechanism and displacement mechanism. The significance of these two mechanisms depends on the mass-damping parameter. The velocity mechanism is dominant for tube arrays with a low mass-damping parameter, and the displacement mechanism is dominant for tube arrays with a high mass-damping parameter. This report presents an experimental and analytical investigation of tube rows in li… more
Date: September 1, 1981
Creator: Chen, S.S. & Jendrzejczyk, J.A.
Partner: UNT Libraries Government Documents Department
open access

Thermal-hydraulic differential sensitivity theory. [LMFBR]

Description: Differential sensitivity theory is applied to a nonlinear, three-dimensional space- and time-dependent description of the thermal-hydraulic conservation equations. The resulting sensitivity equations, which are derived using adjoint functions, can be readily utilized for input parameter sensitivity analysis of large or long-running thermal-hydraulic computer codes without any prior engineering judgement. The procedure for applying this sensitivity theory is illustrated using several classical a… more
Date: September 1, 1981
Creator: Maudlin, P.J.; Parks, C.V. & Weber, C.F.
Partner: UNT Libraries Government Documents Department
open access

Depth-charge static and time-dependence perturbation/sensitivity system for nuclear reactor core analysis. [LMFBR]

Description: This report provides the background theory, user input, and sample problems required for the efficient application of the DEPTH-CHARGE system - a code block for both static and time-dependence perturbation theory and data sensitivity analyses. The DEPTH-CHARGE system is of modular construction and has been implemented within the VENTURE-BURNER computational system at Oak Ridge National Labortary. The DEPTH-CHARGE system provides, for the first time, a complete generalized first-order perturbati… more
Date: September 1, 1981
Creator: White, J.R.
Partner: UNT Libraries Government Documents Department
open access

Correction for gamma-ray self-attenuation in regular heterogeneous materials

Description: A procedure for determining the total correction factor for gamma-ray self-attenuation in regular heterogeneous materials is derived and discussed. The result of a practical application of the procedure to the passive gamma-ray assay of the /sup 235/U content of high-temperature gas reactor fuel is presented.
Date: September 1, 1981
Creator: Parker, J.L.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of the commercial FBR introduction date

Description: This report examines one criterion for introducing a commercial FBR: economic competitiveness with a Light Water Reactor (LWR). For this analysis, the commercial FBR is assumed to be the fifth-of-a kind replicate which represents an economically mature plant. This FBR is deemed economically competitive when its life-cycle energy cost is less than or equal to that of an LWR. Results of this analysis are used in a comparative analysis of alternative FBR development stategies. The strategies evalu… more
Date: September 1, 1981
Creator: White, M.K. & Merrill, E.T.
Partner: UNT Libraries Government Documents Department
open access

Gas-cooled fast reactor program. Progress report, January 1, 1980-June 30, 1981

Description: Since the national Gas-Cooled Fast Breeder Reactor Program has been terminated, this document is the last progress report until reinstatement. It is divided into three sections: Core Flow Test Loop, GCFR shielding and physics, and GCFR pressure vessel and closure studies. (DLC)
Date: September 1, 1981
Creator: Kasten, P. R.
Partner: UNT Libraries Government Documents Department
open access

Human factors engineering control room design review technical evaluation report: Callaway Plant Unit 1

Description: This report identified human engineering discrepancies (HEDs) in Callaway-1. It was found that overall the systems reviewed were designed to permit effective and efficient operator actions. The applicant's proposed resolutions of the HEDs are acceptable to the Human Factors Engineering Branch (HFEB) staff. Because of the large number of systems not available for evaluation during the HFEB site visit, a second visit will be required. (DLC)
Date: September 9, 1981
Creator: Preston, J.
Partner: UNT Libraries Government Documents Department
open access

PADLOC: a one-dimensional computer program for calculating coolant and plateout fission-product concentrations. Part 2

Description: The behavior of some of the prominent fission products along their convection pathways is dominated by the interaction of other species with them. This gave rise to the development of a plateout code capable of analyzing coupled species effects. The single species plateout computer program PADLOC is described in Part I of this report. The present Part II is concerned with the extension of PADLOC to MULTI*PADLOK, a multiple species version of PADLOC. MULTI*PADLOC is designed to analyze the time … more
Date: September 1, 1981
Creator: Hudritsch, W.W.
Partner: UNT Libraries Government Documents Department
open access

Safety concerns and suggested design approaches to the HTGR Reformer process concept

Description: This report is a safety review of the High Temperature Gas-Cooled Reactor Reformer Application Study prepared by Gas-Cooled Reactor Associates (GCRA) of La Jolla, California. The objective of this review was to identify safety concerns and suggests design approaches to minimize risk in the High Temperature Gas-Cooled Reactor Reformer (HTGR-R) process concept.
Date: September 1, 1981
Creator: Green, R.C.
Partner: UNT Libraries Government Documents Department
open access

Worldwide assessment of steam-generator problems in pressurized-water-reactor nuclear power plants

Description: Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of P… more
Date: September 15, 1981
Creator: Woo, H.H. & Lu, S.C.
Partner: UNT Libraries Government Documents Department
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