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in subjects: "Safety Injection"

open access

A level control model for BWR emergency procedure guidelines

The level control during an Anticipated Transient Without Scram (ATWS) event in a BWR as prescribed in the Emergency Procedure Guidelines (EPG) is a difficult task for the operator for he has to keep the water level at the top of active fuel (TAF) without uncovering the reactor core. Also the computer simulation of EPG level control will require many trial and error calculations with the Emergency Core Cooling System (ECCS). A level control system model has been developed and implemented in the… more

Date: October 1, 1996

Creator: Cheng, H.S. & Rohatgi, U.S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the … more

Date: March 1995

Creator: Ware, A. G.; Morton, D. K. & Nitzel, M. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

PIUS scram reactivity analysis

A detailed evaluation of the scram reactivity for the PIUS reactor design has been carried out. The scram reactivity resulting from the injection of highly borated pool water was calculated for a series of time-dependent linear ramp and square-wave pool flows. The three-dimensional core distribution of the pool water was modeled and the spatial reactivity effects of the distributed boron were determined. For pool flows that increase as a linear ramp, the spatial reactivity effects of the distri… more

Date: July 1, 1994

Creator: Carew, J. F.; Selcow, E. C. & Aronson, A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Operating experience of natural circulation core cooling in boiling water reactors

General Electric (GE) has proposed an advanced boiling water reactor, the Simplified Boiling Water Reactor (SBWR), which will utilize passive, gravity-driven safety systems for emergency core coolant injection. The SBWR design includes no recirculation loops or recirculation pumps. Therefore the SBWR will operate in a natural circulation (NC) mode at full power conditions. This design poses some concerns relative to stability during startup, shutdown, and at power conditions. As a consequence, … more

Date: August 1, 1993

Creator: Kullberg, C.; Jones, K. & Heath, C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Evolutionary/advanced light water reactor data report

The US DOE Office of Fissile Material Disposition is examining options for placing fissile materials that were produced for fabrication of weapons, and now are deemed to be surplus, into a condition that is substantially irreversible and makes its use in weapons inherently more difficult. The principal fissile materials subject to this disposition activity are plutonium and uranium containing substantial fractions of plutonium-239 uranium-235. The data in this report, prepared as technical inpu… more

Date: February 9, 1996

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Preliminary systems-interaction results from the Digraph Matrix Analysis of the Watts Bar Nuclear Power Plant safety-injection systems

This report provides preliminary results generated by a Digraph Matrix Analysis (DMA) for a Systems Interaction analysis performed on the Safety Injection System of the Tennessee Valley Authority Watts Bar Nuclear Power Plant. An overview of DMA is provided along with a brief description of the computer codes used in DMA.

Date: June 1, 1983

Creator: Sacks, I.J.; Ashmore, B.C.; Champney, J.M. & Alesso, H.P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Analysis of boron injection transients in pressurized water reactors at natural circulation conditions

The objective of this paper is to analyze boron injection transients at natural circulation conditions in anticipation of preoperational testing in commercial Pressurized Water Reactors (PWRs). The results of the analysis are expected to aid in identifying important phenomena affecting the mixing process and to help to define the measurements needed to assess the results of such tests.

Date: January 1, 1981

Creator: Perkins, K. R.; Bari, R. A. & Cazzoli, E. G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Assessment of thermal fatigue crack propagation in safety injection PWR lines

Cyclic thermal stratification resulting in alternating thermal stresses in pipe cross sections has been identified as the primary cause of high cycle thermal fatigue failure. A number of piping lines in operating plants around the world, susceptible to thermal stratification, have experienced circumferential cracking as a result of high levels of alternating bending stresses. This paper addresses the mechanisms of crack initiation and crack growth and provides estimates of fatigue cycles to fai… more

Date: January 1, 1990

Creator: Simos, N.; Reich, M.; Costantino, C.J. (Brookhaven National Lab., Upton, NY (USA)) & Hartzman, M. (Nuclear Regulatory Commission, Washington, DC (USA). Mechanical Engineering Branch)

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

The effects of aging in component cooling water systems and the implications for life extension

To help assess the effects of aging on safety and reliability, an aging and life extension analysis of component cooling water (CCW) systems in pressurized water reactors (PWRs) has been performed as part of the Nuclear Plant Aging Research (NPAR) program. The NPAR program is sponsored by the NRC Office of Research to provide a technical basis for understanding and managing the effects of aging degradation in nuclear plant applications. The objectives of the two phase CCW system analysis are to… more

Date: January 1, 1991

Creator: Lofaro, R.; Taylor, J. (Brookhaven National Lab., Upton, NY (USA)) & Aggarwal, S. (Nuclear Regulatory Commission, Washington, DC (USA))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

A process for risk-focused maintenance

This report presents a process for focusing maintenance resources on components that enable nuclear plant systems to perform their essential functions and on components whose failure may initiate challenges to safety systems, so as to have the greatest impact in decreasing risk. The process provides criteria, based on risk, for deciding which components are critical to risk and determining what maintenance activities are required to ensure reliable operation of those risk-critical components. T… more

Date: March 1, 1991

Creator: Lofgren, E. V.; Cooper, S. E.; Kurth, R. E. & Phillips, L. B. (Science Applications International Corp., McLean, VA (USA))

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Heavy-Section Steel Technology Program fracture issues

Large-scale fracture mechanics tests have resulted in the identification of a number of fracture-technology issues. Identification of additional issues has come from the reactor vessel materials-irradiation test program and from reactor operating experience. This paper provides a review of fracture issues with an emphasis on their potential impact on a reactor vessel pressurized-thermal-shock (PTS) analysis. Mixed-mode crack propagation emerges as a major issue, due in large measure to the poor… more

Date: January 1, 1991

Creator: Pennell, W.E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Identification and initial assessment of candidate BWR late-phase in-vessel accident management strategies

Work sponsored by the United States Nuclear Regulatory Commission (USNRC) to identify and perform preliminary assessments of candidate BWR (boiling water reactor) in-vessel accident management strategies was completed at Oak Ridge National Laboratory (ORNL) during fiscal year 1990. Mitigative strategies for containment events have been the subject of a companion study at Brookhaven National Laboratory. The focus of this Oak Ridge effort was the development of new strategies for mitigation of th… more

Date: April 15, 1991

Creator: Hodge, S.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Reactor operation safety information document

The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contract… more

Date: January 1, 1990

Item Type: Report

Partner: UNT Libraries Government Documents Department