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Maintenance implementation plan for the Fast Flux Test Facility

Description: This plan implements the U.S. Department of Energy (DOE) 4330.4B, Maintenance Management Program (1994), at the Fast Flux Test Facility (FFTF). The FFTF is a research and test reactor located near Richland, Washington, and is operated under contract for the DOE by the B&W Hanford Company (BWHC). The intent of this Maintenance Implementation Plan (MIP) is to describe the manner in which the activities of the maintenance function are executed and controlled at the FFTF and how this compares to the requirements of DOE 4330.4B. The MIP ii a living document that is updated through a Facility Maintenance Self- Assessment Program. During the continuing self-assessment program, any discrepancies found are resolved to meet DOE 4330.4B requirements and existing practices. The philosophy of maintenance management at the FFTF is also describe within this MIP. This MIP has been developed based on information obtained from various sources including the following: * A continuing self-assessment against the requirements of the Conduct of Maintenance Order * In-depth reviews conducted by the members of the task team that assembled this MIP * Inputs from routine audits and appraisals conducted at the facility The information from these sources is used to identify those areas in which improvements could be made in the manner in which the facility conducts maintenance activities. The action items identified in Rev. 1 of the MIP have been completed. The MIP is arranged in six sections. Section I is this Executive Summary. Section 2 describes the facility and its 0683 history. Section 3 describes the philosophy of the graded approach and how it is applied at FFTF. Section 3 also discusses the strategy and the basis for the prioritizing resources. Section 4 contains the detailed discussion of `the elements of DOE 4330.4B and their state of implementation. Section 5 is for waivers ...
Date: January 30, 1997
Creator: Boyd, J.A.
Partner: UNT Libraries Government Documents Department

A Virtual Reality Framework to Optimize Design, Operation and Refueling of GEN-IV Reactors.

Description: many GEN-IV candidate designs are currently under investigation. Technical issues related to material, safety and economics are being addressed at research laboratories, industry and in academia. After safety, economic feasibility is likely to be the most important crterion in the success of GEN-IV design(s). Lessons learned from the designers and operators of GEN-II (and GEN-III) reactors must play a vital role in achieving both safety and economic feasibility goals.
Date: April 23, 2008
Creator: Rizwan-uddin; Karancevic, Nick; Markidis, Stefano; Dixon, Joel; Luo, Cheng & Reynolds, Jared
Partner: UNT Libraries Government Documents Department

Progress Towards Deployable Antineutrino Detectors for Reactor Safeguards

Description: Fission reactors emit large numbers of antineutrinos and this flux may be useful for the measurement of two quantities of interest for reactor safeguards: the reactor's power and plutonium inventory throughout its cycle. The high antineutrino flux and relatively low background rates means that simple cubic meter scale detectors at tens of meters standoff can record hundreds or thousands of antineutrino events per day. Such antineutrino detectors would add online, quasi-real-time bulk material accountancy to the set of reactor monitoring tools available to the IAEA and other safeguards agencies with minimal impact on reactor operations. Between 2003 and 2008, our LLNL/SNL collaboration successfully deployed several prototype safeguards detectors at a commercial reactor in order to test both the method and the practicality of its implementation in the field. Partially on the strength of the results obtained from these deployments, an Experts Meeting was convened by the IAEA Novel Technologies Group in 2008 to assess current antineutrino detection technology and examine how it might be incorporated into the safeguards regime. Here we present a summary of our previous deployments and discuss current work that seeks to provide expanded capabilities suggested by the Experts Panel, in particular aboveground detector operation.
Date: April 5, 2010
Creator: Bowden, N; Bernstein, A; Dazeley, S; Keefer, G; Reyna, D; Cabrera-Palmer, B et al.
Partner: UNT Libraries Government Documents Department


Description: Advanced reactors are expected to be based on a concept of operations that is different from what is currently used in today's reactors. Therefore, regulatory staff may need new tools, developed from the best available technical bases, to support licensing evaluations. The areas in which new review guidance may be needed and the efforts underway to address the needs will be discussed. Our preliminary results focus on some of the technical issues to be addressed in three areas for which new guidance may be developed: automation and control, operations under degraded conditions, and new human factors engineering methods and tools.
Date: October 1, 2006
Creator: O'HARA, J.; PERSENSKY, J. & SZABO, A.
Partner: UNT Libraries Government Documents Department

SNAPSHOT Safety Program Plan

Description: The SNAPSHOT Safety Program, as described in this document, is therefore formulated to align safety studies performed by separate agencies and their contractors. At the present stage in program development, the plan is principally concerned with the initial SNAPSHOT flight (SNAP 10A). SNAPSHOT represents a special flight mode for the initial reactors operated in space. The flights are designed to permit early space reactor tests prior to resolving all the safety proglems that may be associated with more advanced programs. Of primary significance is that reactor operation will not be initiated until an orbit of satisfactory lifetime has been obtrained, thus ensuring the long-term decay of the fission products producted prior to re-entry.
Date: June 20, 1962
Partner: UNT Libraries Government Documents Department

Technical specifications for the Pajarito Site Critical Experiments Facility

Description: This document is to satisfy the requirement for technical specifications spelled out in ERDA Manual Chapter 0540, ''Safety of ERDA-Owned Reactors.'' Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications replace the document, ''Operating Limits for the Los Alamos Critical Assembly Facility,'' revised May 27, 1971. (auth)
Date: June 1, 1975
Creator: Paxton, H.C.
Partner: UNT Libraries Government Documents Department

Sharing of Rensselaer Polytechnic Institute Reactor Critical Facility (RCF)

Description: The RPI Reactor Critical Facility (RCF) operated successfully over the period fall 1994 - fall 1995. During this period, the RCF was used for Critical Reactor Laboratory spring 1995 (12 students); Reactor Operations Training fall 1994 (3 students); Reactor Operations Training spring 1995 (3 students); and Reactor Operations Training fall 1995 (3 students). Thirty-two Instrumentation and Measurement students used the RCF for one class for hands-on experiments with nuclear instruments. In addition, a total of nine credits of PhD thesis work were carried out at the RCF. This document constitutes the 1995 Report of the Rensselaer Polytechnic Institute`s Reactor Critical Facility (RCF) to the USNRC, to the USDOE, and to RPI management.
Date: November 30, 1995
Partner: UNT Libraries Government Documents Department

Planning and conduct of Operational Readiness Reviews (ORR)

Description: The purpose of this standard is to describe acceptable methods and approaches to meet the readiness review requirements of DOE 425.1. Specifically, this standard describes methods and approaches to: (1) Determine the type of readiness review which is appropriate to the specific facility startup; (2) Develop the breadth and depth (scope) of the ORR or RA so as to be consistent with the history, hazards, and complexity of the facility being started up; (3) Develop the procedures and conduct an ORR or RA for startup of a specific activity; (4) Verify that the facility is physically ready to startup; (5) Verify that the managers and operators are prepared to manage and operate the facility in the phase in which it is about to startup; (6) Verify that the necessary infrastructure (procedures, staffing, compliance with DOE Orders, rules, and other requirements, etc.) is in place; and (7) Prepare requests for exemptions from the requirements of DOE 425.1
Date: November 1, 1995
Partner: UNT Libraries Government Documents Department

TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

Description: This report is a final culmination of activities funded through the Department of Energy`s (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher`s workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead.
Date: May 1, 1997
Creator: Ryan, B.C.
Partner: UNT Libraries Government Documents Department

OSU Reactor Sharing Program FY 1995 annual report

Description: This is the annual report of the activities supported under the Oregon State University Reactor Sharing Program, award number DE-FG06-NE38137. The beginning date for the award was September, 30, 1995 and the end date was September 29, 1996. Work conducted under this award is internally administered at the Radiation Center through a project tasking system. This allows for excellent quality control for the work which is performed from the point of initial contact, through the reactor application, project report generation and financial accounting. For the current fiscal year, FY95, the total cost of the reactor sharing program, including Radiation Center contributions, was $66,323.20 of which $40,000.00 was supplied by the DOE Reactor Sharing Program. The details of individual project costs is given in Table 1. The work performed for the individual projects are described in the brief work descriptions given in Table 2.
Date: October 1, 1996
Creator: Higginbotham, J.F.
Partner: UNT Libraries Government Documents Department

L-Area Cavitation Tests Final Analysis - Limits Application

Description: The L-Area cavitation test was designed to better define the onset of cavitation in the reactor system. The onset of gas evolution in the effluent piping and pump cavitation was measured using state-of-the-art equipment to provide data with a high confidence and low uncertainty level. The limits calculated from the new data will allow an approximate two percent increase in reactor power if the reactor is effluent temperature-limited with no compromise in reactor safety.
Date: June 26, 2001
Creator: Wood, D.C.
Partner: UNT Libraries Government Documents Department

Final Report: Reactor Sharing, September 30, 1996 - September 29, 1998

Description: Under the support provided by the DOE Reactor Sharing Program the Reactor Laboratory has provided tours, lectures, and demonstrations in support of science teaching in Arizona high schools. The reactor has also been used in a very successful summer program to encourage high school students who are members of population groups underrepresented in engineering to consider careers in engineering fields. This program is in the form of one or two week on-campus workshops given several times each summer to students at different levels of junior or senior high school. The Reactor Laboratory was one of six or eight areas of engineering to which the participants were introduced. The degree of involvement ranged from tours and demonstrations of reactor operation in small groups for the younger students, to neutron activation analysis experiments, with student participation, at the higher grade levels. The reactor time funded by this DOE grant has provided significant service to students and faculty from other educational institutes using our facilities. In addition, we have had the opportunity to provide public education in nuclear reactor science and engineering to a wide variety of groups, especially school children.
Date: October 28, 1999
Creator: Williams, John G.
Partner: UNT Libraries Government Documents Department

System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2

Description: The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors.
Date: November 1, 2000
Creator: Ellis, R.J.
Partner: UNT Libraries Government Documents Department

Perspectives on Low Power and Shutdown Risk

Description: This paper presents results from a program sponsored by the US Nuclear Regulatory Commission to examine the risks from low power and shutdown operations. Significant progress has been made by the industry in reducing such risks; however, important operational events continue to occur. Current perceptions of low power and shutdown risks are discussed in the paper along with an assessment of the current methods for understanding important events and quantifying their associated risk.
Date: July 6, 2000
Partner: UNT Libraries Government Documents Department

Technical safety requirements for the Annular Core Research Reactor Facility (ACRRF)

Description: The Technical Safety Requirements (TSR) document is prepared and issued in compliance with DOE Order 5480.22, Technical Safety Requirements. The bases for the TSR are established in the ACRRF Safety Analysis Report issued in compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports. The TSR identifies the operational conditions, boundaries, and administrative controls for the safe operation of the facility.
Date: January 1, 1998
Creator: Boldt, K.R.; Morris, F.M.; Talley, D.G. & McCrory, F.M.
Partner: UNT Libraries Government Documents Department

Reactor operations informal monthly report, May 1, 1995--May 31, 1995

Description: This document is an informal progress report for the operational performance of the Brookhaven Medical Research Reactor, and the Brookhaven High Flux Beam Reactor, for the month of May, 1995. Both machines ran well during this period, with no reportable instrumentation problems, all scheduled maintenance performed, and only one reportable occurance, involving a particle on Vest Button, Personnel Radioactive Contamination.
Date: May 1, 1995
Creator: Hauptman, H.M.; Petro, J.N. & Jacobi, O.
Partner: UNT Libraries Government Documents Department

Advanced reactors transition fiscal year 1996 multi-year program plan WBS 7.3

Description: This document describes in detail the work to be accomplished in FY 1996 and the out years for the Advanced Reactors Transition (WBS 7.3. ). This document describes specific milestones and funding profiles. Based upon the Fiscal Year 1996 Multi-Year Program Plan (MYPP), DOE will provide authorization to perform the work outlined in the FY 1996 MYPP
Date: September 21, 1995
Creator: Hulvey, R.K.
Partner: UNT Libraries Government Documents Department

Fast Flux Test Facility (FFTF) standby plan

Description: The FFTF Standby Plan, Revision 0, provides changes to the major elements and project baselines to maintain the FFTF plant in a standby condition and to continue washing sodium from irradiated reactor fuel. The Plan is consistent with the Memorandum of Decision approved by the Secretary of Energy on January 17, 1997, which directed that FFTF be maintained in a standby condition to permit the Department to make a decision on whether the facility should play a future role in the Department of Energy`s dual track tritium production strategy. This decision would be made in parallel with the intended December 1998 decision on the selection of the primary, long- term source of tritium. This also allows the Department to review the economic and technical feasibility of using the FFTF to produce isotopes for the medical community. Formal direction has been received from DOE-RL and Fluor 2020 Daniel Hanford to implement the FFTF standby decision. The objective of the Plan is maintain the condition of the FFTF systems, equipment and personnel to preserve the option for plant restart within three and one-half years of a decision to restart, while continuing deactivation work which is consistent with the standby mode.
Date: March 6, 1997
Creator: Hulvey, R.K.
Partner: UNT Libraries Government Documents Department

National Ignition Facility (NIF) operations procedures plan

Description: The purpose of this Operations Procedures Plan is to establish a standard procedure which outlines how NIF Operations procedures will be developed (i.e , written, edited, reviewed, approved, published, revised) and accessed by the NIF Operations staff who must use procedures in order to accomplish their tasks. In addition, this Plan is designed to provide a guide to the NIF Project staff to assist them in planning and writing procedures. Also, resource and scheduling information is provided.
Date: May 6, 1998
Creator: Mantrom, D.
Partner: UNT Libraries Government Documents Department