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in subjects: "220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors"

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Fuel pin fabrication for the FFTF

Fabrication processes for FFTF fuel pins are described.

Date: January 1, 1980

Creator: Williams, J.F. & Rice, L.H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

LOFT Vital MG Set transient parameter review

This report evaluates the performance of the vital MG sets during a worst case load transfer. Evaluation of test data showed: (1) The Vital MG Set withstood the extreme loading; (2) The load can be sustained well in excess of the required time limit; and (3) The transfer perturbation caused the frequency to exceed the limits set by the SDD. The follow up evaluations of the equipment powered by the MG sets demonstrated that the equipment function will not be degraded.

Date: September 12, 1978

Creator: Kranning, A.N.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Stress analysis of conical flued heads for FFTF liquid metal piping anchors

Flued heads for liquid metal piping were designed to function as structural anchors for liquid metal piping and as atmospheric seals between compartments. Their design was complicated by the need to provide high strength and rigidity as piping anchors, yet to have the flexibility needed to accommodate severe thermal differential temperature gradients under both steady state and transient conditions. Conical flued head design configurations in sizes from 1'' to 28'' were evol… more

Date: March 1, 1979

Creator: Sampson, R. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Closed Loop In-Reactor Assembly (CLIRA): a fast flux test facility test vehicle

The Closed Loop In-Reactor Assembly (CLIRA) is a test vehicle for in-core material and fuel experiments in the Fast Flux Test Facility (FFTF). The FFTF is a fast flux nuclear test reactor operated for the Department of Energy (DOE) by Westinghouse Hanford Company in Richland, Washington. The CLIRA is a removable/replaceable part of the Closed Loop System (CLS) which is a sodium coolant system providing flow and temperature control independent of the reactor coolant system. The primary purpose o… more

Date: September 12, 1978

Creator: Oakley, D.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

LOFT CIS analysis: 1''-PCC-76-A inside containment penetration S-1A. Internal technical report

The stress analysis performed on the 1''-PCC-76-A piping system inside containment penetration S-1A is described. Deadweight, thermal expansion, and seismic loads were considered. Results of this analysis show that the subject piping system will meet ASME Boiler and Pressure Vessel Code, Section III, Class 2 requirements provided that supports S8 and S9 are installed as recommended.

Date: December 11, 1978

Creator: Nitzel, M.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

LOFT reactor advanced instrumented center fuel bundle

The program for designing and fabricating replacement fuel modules for LOFT provides a method for incorporating improvements in contemporary LPWR fuel design and in-reactor measurement techniques. Special development projects for measurement devices support the LOFT replacement fuel program.

Date: January 1, 1979

Creator: Howell, T. E. & Selcho, H. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

FFTF regulatory review for operating authorization

The Project has undertaken design studies of concepts capable of providing added containment safety margins. Since the events, for which these features provide consequence reductions, are beyond the design basis accident classification, the conceptual designs would not be designed as Engineered Safety Features. A final decision has not been made by the Department of Energy as to the disposition of this advice. It is the Project's plan to develop sufficient design details for these features… more

Date: January 1, 1979

Creator: Schade, A. R. & Simpson, D. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Instrument calibration program for startup on FFTF

Calibration of plant instruments and control equipment is a key plant startup activity. Clearly defined calibration requirements are needed to effectively guide this activity. A master-loop/sub-loop concept developed for use at the FFTF to help solve this problem is described. Startup testing methods related to the calibration activity are also described and critiqued.

Date: June 1, 1979

Creator: Swanson, C. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

DALIS: a computer-assisted document retrieval system for the FFTF

The FFTF (Fast Flux Test Facility) is a liquid sodium cooled, fast flux reactor designed specifically for irradiation testing of fuels and components for liquid metal fast breeder reactors. The Department of Energy and the Nuclear Regulatory Commission require that all pertinent documentation for maintenance, operation, and safety of the FFTF be readily accessible and retrievable, both during initial startup and for the lifetime of the plant. That amounts to a lot of information which has to be… more

Date: May 12, 1981

Creator: Harves, W G

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Structural material irradiations in FFTF

Information is presented concerning the Materials Open Test Assembly (MOTA); instrumentation and control system; MOTA neutronic data; pressurized tube specimens; stress-rupture measurements for reactor materials; miniature specimen design; the Interim Examination and Maintenance (IEM) cell at the FFTF; support services; and general information concerning the FFTF.

Date: January 1, 1985

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Experience in the use of FBR core component structural design criteria as applied to FFTF

User gained experience resulting from trial applications of proposed structural design guidelines for Fast Breeder Reactor (FBR) core components is presented. This work was done supporting the design analyses process for consumable core components for the Fast Test Reactor (FTR) of the Fast Flux Test Facility (FFTF). The proposed guidelines were found to be more comprehensive and generally easier to apply than those methods previously used. Component evaluation required a minimum amount of deta… more

Date: January 1, 1979

Creator: Hecht, S.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Experience with simplified inelastic analysis of FFTF test assemblies

Included in the more recent design activities for the Fast Flux Test Facility (FFTF) are a series of test assemblies which will contain experiments in the FFTF reactor. Due to high operating temperatures and severe thermal transients, inelastic analysis is generally required to demonstrate structural adequacy. Based upon previous FFTF experience, a number of simplifications have been made to reduce the inelastic analysis effort. Significant time and cost savings have resulted.

Date: February 1, 1979

Creator: Winkel, B. V.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

High temperature testing of a sodium pump. ASME Publication No. 78-WA/NE-12

Problems encountered during high temperature sodium testing of a prototype breeder reactor heat transport pump at the Energy Technology Engineering Center (ETEC) are discussed. Special tests and analyses to resolve the uneven heating and resulting high shaft torque which was traced to cellular natural convection is discussed. Vibrations were observed during steady-state testing. Diagnostic testing and analyses (e.g., power spectral density) were developed to determine the source and to effect a… more

Date: January 1, 1978

Creator: Atz, R.W. & Tessier, M.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Handling of sodium for the FFTF

Based on the High Temperature Sodium Facility (HTSF) experience and the extensive design efforts for FFTF, procedures are in place for the unloading of the tank cars and for the fill of the FFTF reactor. Special precautions have been taken to provide safe handling and to accommodate contingencies in operation. These contingencies include special protective suits allowing personnel to enter and correct conditions arising from fill operations in the course of moving 7.71 x 10/sup 5/ kg (1.7 x 10/… more

Date: June 1, 1978

Creator: Ballif, J.L. & Meadows, G.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Investigation of effect of single phase electrical faults at LOFT

This LTR presents the general basic engineering facts related to an open phase fault in a three phase power system commonly referred to as a single phase condition. It describes the probable results to electrical motors and describes the LOFT system design factors which minimize the likelihood of such a fault occurring at LOFT. It recognizes that the hazard of such a fault is a realistic threat and notes the types of relays designed to provide protection. Recommendations are made to perform a d… more

Date: September 28, 1978

Creator: Yeates, J. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Integrated leak rate testing of the fast flux test facility reactor containment building

The initial Integrated Leak Rate Test (ILRT) of the Fast Flux Test Facility containment building was performed from May 27 to June 2, 1978. The test was conducted in air with systems vented and with the containment recirculating coolers in operation. 10 psig and 5 psig tests were run using the absolute pressure test method. The measured leakage rates were .033% Vol/24 hr. and -.0015% Vol/24 hrs. respectively. Subsequent verification tests at both 10 psig and 5 psig proved that the test equipmen… more

Date: January 1, 1978

Creator: James, E. B.; Farabee, O. A. & Bliss, R. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

LOFT CIS Analysis Line 2 inches-IA-298-AB outside containment penetration S-2A

Line 2''-IA-295-AB outside containment penetration S-2A was analyzed to ASME Section III, Subsection NC (Class 2) criteria. The line is part of the Containment Isolation System. The model considered the line from the penetration outward through the first isolation valve. Results of the analysis show that this section of the line meets Class 2 requirements without modification.

Date: September 12, 1978

Creator: Pierce, A.T.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Low-Enrichment Fuel Development Program

The national program of the Department of Energy at Argonne National Laboratory for the development of highly loaded uranium fuels, which provide the means for enrichment reduction, has been briefly described. The objectives of > 60 wt % uranium in plate-type fuels and greater than or equal to 45 wt % uranium in U--ZrH/sub x/ rod-type fuels are expected to be met. The most promising fuels will be further evaluated in full-size element irradiations and whole-core demonstrations on the route towa… more

Date: January 1, 1978

Creator: Stahl, D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

FFTF EM service pump design, application, and testing

During 1975, HEDL selected Atomics International to review the design of three classes of EM Pumps (L-30, L-100, L-200) and to fabricate a total of fifteen pumps. One of the L-100 pumps was shipped to the liquid Metal Engineering Center (LMEC) for sodium testing in the small components test loop (SCTL). The paper presents the HEDL design criteria, discusses the resulting design, and reviews the test results against the predictions.

Date: January 1, 1977

Creator: Jacobson, G.; Carter, E. H.; Hallinan, G. J. & Eichelberger, R. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Benchmark revisited: the accuracy of finite difference methods and the potential for the use of nodal methods in the analyses of research and test reactors

Nodal methods are tested for use in the neutronics analysis of research reactors. The results are compared to finite difference methods in both cost and accuracy. Transport effects and nodal transport are also considered. The IAEA benchmark reactor has been used as a base for this assessment. The nodal method was found to be very effective in reducing computation costs, and the accuracy of the solution is often higher than that attained with finite difference. In fact, in order to have a finite… more

Date: January 1, 1985

Creator: Woodruff, W.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Oak Ridge Research Reactor shutdown maintenance and surveillance

The Department of Energy ordered the Oak Ridge Research Center Reactor to be placed in permanent shutdown on July 14, 1987. Maintenance activities, both mechanical and instrument, were essentially routine in nature. The performance of the instrumentation for the facility was satisfactory, and maintenance required is provided. The performance of the process system was satisfactory, and maintenance required is indicated. The results of efficiency tests of the various gaseous-waste filters have be… more

Date: October 1, 1990

Creator: Coleman, G.H. & Laughlin, D.L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

LOFT CIS analysis 2''-IA-299-AB inside containment penetration S-5B

A stress analysis was performed on the 2''-IA-299-AB pipe system inside containment penetration S-5B. Deadweight, thermal expansion and seismic loads were considered. The results indicate that this piping will meet ASME Section III, Class 2 requirements.

Date: September 12, 1978

Creator: Morton, D.K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Analysis of debris vacuumed from K-Reactor tank

During the ultrasonic (UT) inspection of K-Reactor tank by the Equipment Engineering Section in the spring of 1990, solid material (termed debris) was seen on the bottom of the tank. When the UT inspection was complete, a specially designed underwater vacuum cleaner was used to collect the accumulation at 17 monitor pin positions. This material was sent to SRL for characterization as an action item of the Reactor Corrosion Mitigation Committee. Acquisition of this debris provided an opportunity… more

Date: January 20, 1992

Creator: Baumann, E. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

FFTF operating and administrative index

No Description Available.

Date: October 15, 1976

Item Type: Report

Partner: UNT Libraries Government Documents Department