165 Matching Results

Search Results

Advanced search parameters have been applied.

in subjects: "Feedwater"

open access

Aging assessment of auxiliary feedwater systems

A study of Pressurized Water Reactor Auxiliary Feedwater (AFW) Systems has been conducted by Oak Ridge National Laboratory (ORNL) under the auspices of the Nuclear Regulatory Commission's Nuclear Plant Aging Research Program. The study has reviewed historical failure experience and current monitoring practices for the AFW System. This paper provides an overview of the study approach and results. 7 figs.

Date: January 1, 1989

Creator: Casada, D.A. (Oak Ridge National Lab., TN (USA))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Distributed and hierarchical control techniques for large-scale power plant systems

In large-scale systems, integrated and coordinated control functions are required to maximize plant availability, to allow maneuverability through various power levels, and to meet externally imposed regulatory limitations. Nuclear power plants are large-scale systems. Prime subsystems are those that contribute directly to the behavior of the plant's ultimate output. The prime subsystems in a nuclear power plant include reactor, primary and intermediate heat transport, steam generator, turbine … more

Date: August 1, 1985

Creator: Raju, G. V. S. & Kisner, R. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

March 1982 environmental data for sites in the National Solar Data Network

Environmental information collected at the sites of the National Solar Data Network is presented in the form of tables for each solar site. The sites are grouped into 12 zones, each of which consists of several adjacent states. The insolation table presents the total, diffuse, direct, maximum, and extraterrestrial radiation for the solar site. It also shows the ratio of total to extraterrestrial radiation as a percent. The temperature table gives the average, daytime, nighttime, maximum, minimu… more

Date: March 1, 1982

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Evaluation of cracking in feedwater piping adjacent to the steam generators in Nine Pressurized Water Reactor Plants

Cracking in ASTM A106-B and A106-C feedwater piping was detected near the inlet to the steam generators in a number of pressurized water reactor plants. We received sections with cracks from nine of the plants with the objective of identifying the cracking mechanism and assessing various factors that might contribute to this cracking. Variations were observed in piping surface irregularities, corrosion-product, pit, and crack morphology, surface elmental and crystal structure analyses, and stee… more

Date: June 25, 1980

Creator: Goldberg, A.; Streit, R. D. & Scott, R. G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Feed-pump hydraulic performance and design improvement, Phase I: research program design. Final report. Volume 2

As a result of prior EPRI-sponsored studies, it was concluded that a research program should be designed and implemented to provide an improved basis for the design, procurement, testing, and operation of large feed pumps with increased reliability and stability over the full range of operating conditions. This two-volume report contains a research plan which is based on a review of the present state of the art and which defines the necessary R and D program and estimates the benefits and costs… more

Date: March 1, 1982

Creator: Brown, W. H.; Gopalakrishnan, S.; Fehlau, R.; Thompson, W. E. & Wilson, D. G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Environmental data for sites in the National Solar Data Network

Date: June 1, 1981

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Safety implications of control systems

The Safety Implications of Control Systems Program has three major activities in support of USI-A47. The first task is a failure mode and effects analysis of all plant systems which may potentially induce control system disturbance that have safety implications. This task has made a preliminary study of overfill events and recommended cases for further analysis on the hybrid simulator. Work continues on overcooling and undercooling. A detailed investigation of electric power network is in progr… more

Date: January 1, 1983

Creator: Smith, O.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Evaluation of condensation-induced water hammer in preheat steam generators

A review of Westinghouse 1/8-scale water hammer tests and data analysis was carried out. BNL has concluded that water hammers occurred in the feedwater line during many of the 1/8-scale tests. These events were probably caused by steam bubble entrapment and collapse in the partially-filled feedwater line. Recorded vessel pressure pulse activity under two-phase operating conditions was rare and, in those cases where pulses were recorded, the pressure pulse amplitudes were small. Either void coll… more

Date: September 1, 1980

Creator: Saha, P.; Ginsberg, T.; Wu, B.J.C. & Jones, O.C. Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Development and testing of a diagnostic system for intelligen distributed control at EBR-2

A diagnostic system is under development for demonstration of Intelligent Distributed Control at the Experimental Breeder Reactor (EBR--II). In the first phase of the project a diagnostic system is being developed for the EBR-II steam plant based on the DISYS expert systems approach. Current testing uses recorded plant data and data from simulated plant faults. The dynamical simulation of the EBR-II steam plant uses the Babcock and Wilcox (B W) Modular Modeling System (MMS). At EBR-II the diagn… more

Date: January 1, 1990

Creator: Edwards, R.M.; Ruhl, D.W.; Klevans, E.H. & Robinson, G.E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Investigation of pressure transient propagation in pressurized water reactor feedwater lines

Results are reported of a study for the Nuclear Regulatory Commission (NRC) to provide a general understanding of pressure transient (water hammer) propagation in pressurized water reactor (PWR) steam generator feedwater piping systems. A typical feedwater network is defined, and pressure transient initiation is discussed, as well as the plausible pulse shapes reported. The analysis is performed by using the computer codes PTA and WHAM. Forces are calculated at elbows and valves by using moment… more

Date: July 22, 1977

Creator: Sutton, S. B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

SASSYS-1 balance-of-plant component models for an integrated plant response

Models of power plant heat transfer components and rotating machinery have been added to the balance-of-plant model in the SASSYS-1 liquid metal reactor systems analysis code. This work is part of a continuing effort in plant network simulation based on the general mathematical models developed. The models described in this paper extend the scope of the balance-of-plant model to handle non-adiabatic conditions along flow paths. While the mass and momentum equations remain the same, the energy e… more

Date: January 1, 1989

Creator: Ku, J.-Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Piping-reliability analysis for pressurized-water-reactor feedwater lines

This paper presents a piping reliability analysis for feedwater lines at five PWR plants; the analysis is based on probabilistic fracture mechanics. On the basis of observed pipe cracks in these feedwater lines, the crack is modeled with an initial semi-elliptical shape along the pipe inner circumference. Initial crack samples are generated using the Monte Carlo technique in conjunction with an importance sampling scheme. The fatigue model for crack growth employs a Paris-type growth-rate equat… more

Date: January 1, 1982

Creator: Woo, H.H. & Chou, C.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

San Onofre/Zion auxiliary feedwater system seismic fault tree modeling

As part of the study for the seismic evaluation of the San Onofre Unit 1 Auxiliary Feedwater System (AFWS), a fault tree model was developed capable of handling the effect of structural failure of the plant (in the event of an earthquake) on the availability of the AFWS. A compatible fault tree model was developed for the Zion Unit 1 AFWS in order to compare the results of the two systems. It was concluded that if a single failure of the San Onofre Unit 1 AFWS is to be prevented, some weight ex… more

Date: February 1, 1982

Creator: Najafi, B. & Eide, S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

TRAC-PF1 analysis of LOFT steam-generator feedwater transient test L9-1. [PWR]

The Transient Reactor Analysis Code (TRAC-PF1) calculations were compared to test data from Loss-of-Fluid Test (LOFT) L9-1, which was a loss-of-feedwater transient. This paper includes descriptions of the test and the TRAC input and compares the TRAC-calculated results with the test data. We conclude that the code predicted the experiment well, given the uncertainties in the boundary conditions. The analysis indicates the need to model all the flow paths and heat structures, and to improve the … more

Date: January 1, 1983

Creator: Meier, J.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Uncertainty in BWR power during ATWS events

A study was undertaken to improve our understanding of BWR conditions following the closure of main steam isolation valves and the failure of reactor trip. Of particular interest was the power during the period when the core had reached a quasi-equilibrium condition with a natural circulation flow rate determined by the water level in the downcomer. Insights into the uncertainity in the calculation of this power with sophisticated computer codes were quantified using a simple model which relate… more

Date: January 1, 1986

Creator: Diamond, D. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fresnel/photovoltaic concentrator application experiment for the Dallas-Fort Worth airport. Phase 1: system design, final technical report, 1 June 1978-28 February 1979

This Phase I Final Report summarizes the analytical, experimental, design, and specification efforts for the first nine months of the Dallas/Fort Worth Airport Fresnel/Photovoltaic Concentrator Application Experiment. The overall objective of the complete three-phase program is to develop and demonstrate a unique photovoltaic concentrator total energy system which, when mass-produced, will provide electrical and thermal energy at costs competitive with conventional energy sources. Toward this o… more

Date: March 1, 1979

Creator: O'Neill, M. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Rapid-response analysis of the Davis-Besse loss-of-feedwater event on June 9, 1985

At the request of the US Nuclear Regulatory Commission (NRC), we performed a rapid-response analysis of the loss-of-feedwater (LOFW) event that occurred at the Toledo Edison Davis-Besse plant on June 9, 1985. The initial 831 s of the plant transient were simulated and, in addition, four postulated transients were calculated to determine how the plant would have responded if feedwater had not been restored, and how it would have responded to a feed-and-bleed (FAB) decay-heat removal procedure in… more

Date: January 1, 1986

Creator: Lime, J. F.; Nassersharif, B. & Boyack, B. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Auxiliary feedwater system risk-based inspection guide for the Byron and Braidwood nuclear power plants

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC fo… more

Date: July 1, 1991

Creator: Moffitt, N.E. & Gore, B.F.: Vo, T.V. (Pacific Northwest Lab., Richland, WA (USA))

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Flooding Experiments and Modeling for Improved Reactor Safety

Countercurrent two-phase flow and “flooding” phenomena in light water reactor systems are being investigated experimentally and analytically to improve reactor safety of current and future reactors. The aspects that will be better clarified are the effects of condensation and tube inclination on flooding in large diameter tubes. The current project aims to improve the level of understanding of flooding mechanisms and to develop an analysis model for more accurate evaluations of flooding in the … more

Date: September 14, 2008

Creator: Solmos, M., Hogan, K.J., VIerow, K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

A Automated Tool for Supporting FMEAs of Digital Systems

Although designs of digital systems can be very different from each other, they typically use many of the same types of generic digital components. Determining the impacts of the failure modes of these generic components on a digital system can be used to support development of a reliability model of the system. A novel approach was proposed for such a purpose by decomposing the system into a level of the generic digital components and propagating failure modes to the system level, which genera… more

Date: September 7, 2008

Creator: Yue, M.; Chu, T. L.; Martinez-Guridi, G. & Lehner, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Analysis of steam-generator tube-rupture events combined with auxiliary-feedwater control-system failure for Three Mile Island-Unit 1 and Zion-Unit 1 pressurized water reactors

A steam-generator tube-rupture (SGTR) event combined with loss of all offsite alternating-current power and failure of the auxiliary-feedwater (AFW) control system has been investigated for the Three Mile Island-Unit 1 (TMI-1) and Zion-Unit 1 (Zion-1) pressurized water reactors. The Transient Reactor Analysis Code was used to simulate the accident sequence for each plant. The objectives of the study were to predict the plant transient response with respect to tube-rupture flow termination, exte… more

Date: January 1, 1986

Creator: Nassersharif, B.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Evaluation of cracking in steam generator feedwater piping in pressurized water reactor plants

Cracking in feedwater piping was detected near the inlet to steam generators in 15 pressurized water reactor plants. Sections with cracks from nine plants are examined with the objective of identifying the cracking mechanism and assessing various factors that might contribute to this cracking. Using transmission electron microscopy, fatigue striations are observed on replicas of cleaned crack surfaces. Calculations based on the observed striation spacings gave a cyclic stress value of 150 MPa (… more

Date: May 1, 1981

Creator: Goldberg, A. & Streit, R. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Simulations of the recent Lasalle-2 incident with the BNL plant analyzer

This paper presents the results of simulations of the recent power oscillation incident at the LaSalle-2 Nuclear Power Plant using the BNL Plant Analyzer. The causes of the oscillation were investigated and the sensitivity of the oscillation to key parameters was studied. It is concluded that the observed power oscillation was caused by boiling instability (i.e., density wave oscillation) reinforced by the reactivity feedback in neutron kinetics, and that the density wave oscillation resulted f… more

Date: January 1, 1989

Creator: Chang, H.S.; Mallen, A.N. & Wulff, W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Integrated TRAC/MELPROG analysis of core damage from a severe feedwater transient in the Oconee-1 PWR

A postulated complete loss-of-feedwater event in the Oconee-1 pressurized water reactor has been analyzed. With an initial version of the lonked TRAC and MELPROG codes, we have modeled the loss-of-feedwater event from initiation to the time of complete disruption of the core, which was calculated to occur by 6800 s. The highest structure temperatures otuside the vessel are on the flow path from the vessel to the pressurizer relief valve. Temperatures in excess of 1200 K could result in failure … more

Date: January 1, 1986

Creator: Henninger, R. J. & Boyack, B. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department