662 Matching Results

Search Results

Advanced search parameters have been applied.

in publisher: "Hanford Engineering Development Laboratory"

open access

Neutron environment in d + Li facilities

A microscopic d + Li neutron yield model has been developed based upon classical models and experimental data. Using equations suggested by the Serber and evaporation models, a generalized least squares adjustment procedure generated angular yields for E/sub d/ to 40 MeV using the available experimental data. The HEDL-UCD experiment at E/sub d/ = 35 was used to adjust parameters describing the neutron spectra. The model is used to predict yields, spectra, and damage responses in the FMIT Test C… more

Date: January 1, 1980

Creator: Mann, F. M.; Schmittroth, F. & Carter, L. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Irradiation experiment for lithium ceramics

Solid breeder materials are required in D-T fusion reactor blankets to convert fusion neutrons to tritium and thermal energy while providing some neutron shielding for the magnets. Lithium compounds such as Li/sub 2/O, LiAlO/sub 2/, Li/sub 4/SiO/sub 4/ and Li/sub 2/ZrO/sub 3/ have been proposed as solid breeder materials. Tritium is necessary to maintain the fuel supply for the D-T fusion reaction. No high burnup irradiation performance data is available for these materials in a neutron environ… more

Date: March 1, 1982

Creator: Hollenberg, G.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Deposition and removal of radioactive isotopes from LMFBR components

The development of an analytical model to describe the production, transport and eventual removal of radioactive materials in the primary sodium of LMFBR's is a continuing Sodium Technology activity sponsored by the Department of Energy. This paper describes studies directed toward obtaining an understanding of the deposition from sodium of fuel cladding activated corrosion products onto stainless steel alloys and the effect of their diffusion into the base metal on the process required to deco… more

Date: January 1, 1980

Creator: Hill, E. F.; Lutton, J. M. & Maffei, H. P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

High-temperature of thermodynamic properties of sodium

The set of high-temperature thermodynamic properties for sodium in the two-phase and subcooled-liquid regions which was previously recommended, has been modified to incorporate recent experimental data. In particular, replacement of the previously estimated critical constants with experimentally-determined values has resulted in substantial differences in the region of the critical point. The following thermodynamic properties were determined: pressure, density, enthalpy, entropy, internal ener… more

Date: January 1, 1977

Creator: Padilla, A. Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Silicon mass transfer in sodium loops and the resulting/thermal hydraulic effects. [LMFBR]

The element silicon in the surface of new, 300 series stainless steel has been shown to rapidly dissolve in sodium above 525/sup 0/C. It deposits in slightly cooler regions as a crystalline compound with sodium and oxygen. In tests, the deposits have caused increases in hydraulic friction factor (hence, increased pressure loss) of up to 300% at Reynolds Numbers of 14/sup 4/ to 10/sup 5/.Also, they have contributed to local losses of heat transfer rate to 1/10 the original value, at a Reynolds N… more

Date: February 1, 1980

Creator: Yunker, W.H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Sodium compatibility of HT-9 and Fe-9Cr-1Mo steels

Ferritic steels have been receiving significant attention for possible use as steam generator tubing, and as alternate structural materials for liquid-metal heat-transport systems in commercial fast reactors, fusion reactors, etc. The materials are chosen on the basis of their high thermal conductivity, resistance to stress-corrosion-cracking in aqueous and steam environments, favorable fabricability and fairly low cost. These steels are available in several classes based on the microstructure … more

Date: November 1, 1985

Creator: Anantatmula, R. P. & Brehm, W. F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Review of water resource potential for developing geothermal resource sites in the western United States

Water resources at 28 known geothermal resource areas (KGRAs) in the western United States are reviewed. Primary emphasis is placed upon examination of the waer resources, both surface and ground, that exist in the vicinity of the KGRAs located in the southwestern states of California, Arizona, Utah, Nevada, and New Mexico. In most of these regions water has been in short supply for many years and consequently a discussion of competing demands is included to provide an appropriate perspective o… more

Date: July 1, 1980

Creator: Sonnichsen, J.C. Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Time series analysis of reactor thermocouple data. [LMFBR]

Time-series analysis techniques are applied to nuclear reactor thermocouple data to investigate coolant temperatures measured within the fueled test assembly. The coolant temperature distribution within a fuel assembly affects the length of time a fuel assembly may be operated in a power reactor and, therefore, is an important economic consideration in the design of reactor fuel systems. Frequency-domain signal conditioning techniques were used to reveal the smoothly varying thermocouple signal… more

Date: April 10, 1980

Creator: Devary, J.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Nuclear data relevant to shield design of FMIT facility

Nuclear data requirements are reviewed for the design of the Fusion Materials Irradiation Test (FMIT) facility. This accelerator-based facility, now in the early stages of construction at Hanford, will provide high fluences in a fusion-like radiation environment for the testing of materials. The nuclear data base required encompasses the entire range of neutron energies from thermal to 50 MeV. In this review, we consider neutron source terms, cross sections for thermal and bulk shield design, a… more

Date: January 1, 1980

Creator: Carter, L. L.; Morford, R. J. & Wilcox, A. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Rod scanner assay of FFTF fuel

Rod scanner results for over 40,000 FFTF Cores 1 and 2 fuel pins are summarized. An improved rod scanner calibration technique for FFTF Cores 3 and 4 fuel pins is described. Data are compared with chemical assay measurements. 5 fig., 5 tables.

Date: January 1, 1978

Creator: Goris, P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Postirradiation cladding strength under biaxial loading with an increasing temperature ramp. [LMFBR]

The flow behavior of unirradiated 20% cold worked AISI 316 tubing during constant pressure, increasing temperature tests was modeled with a constitutive relation approach; strain below approximately 0.2% came predominantly from an anelastic portion of the model while higher strains were predominantly plastic. The flow of cladding sections from irradiated fuel pins was largely restricted to the strain region attributed to anelastic deformation due to reduced ductility compared to unirradiated tu… more

Date: April 1, 1980

Creator: Duncan, D. R. & Hunter, C. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Comparison of aerosol behavior during sodium fires in CSTF with the HAA-3B code. [LMFBR]

Four large-scale tests using sodium fire aerosol sources have been carried out in the Containment System Test Facility (CSTF). Two of the tests employed pool fires and two used spray fires as the aerosol source. Because the CSTF containment vessel is approximately half-scale (20.3 m in height) of a typical reactor building, the CSTF results have provided a large-scale proof test of the HAA-3B Code. For the two pool fire tests, the measured and predicted airborne concentrations were in good agre… more

Date: March 1, 1980

Creator: Postma, A.K. & Owen, R.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Acoustic Emission Weld Monitoring of Nuclear Components

Acoustic emission monitoring augments other nondestructive testing methods and is sometimes applicable when other tests cannot be applied. This is, in part, due to the high sensitivity of acoustic emission monitoring. Acoustic emission monitoring is only sensitive to active flaw-growth, however, and will not detect a flaw in equilibrium. This paper describes the application of acoustic emission monitoring to nuclear reactor fuel pin end closure welds and other weldments of the reactor piping.

Date: January 25, 1972

Creator: Romrell, D. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Comparative analysis of internal fuel motion in annular fuel designs

In this paper, the whole-core reactivity consequences of internal fuel motion in three annular fuel designs during a hypothetical 3 dollars/s transient overpower (TOP) accident are compared to determine the effect of geometric design variations. The PINEX-2 and PINEX-3 experiments were performed in the TREAT reactor using annular fuel pins irradiated in GETR. This paper investigates three combinations of solid and annular axial blankets and fission gas plena: top annular blanket and plenum, bot… more

Date: September 16, 1983

Creator: Smith, D. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fuel systems for compact fast space reactors

About 200 refractory metal clad ceramic fuel pins have been irradiated in thermal reactors under the 1200 K to 1550 K cladding temperature conditions of primary relevance to space reactors. This paper reviews performance with respect to fissile atom density, operating temperatures, fuel swelling, fission gas release, fuel-cladding compatibility, and consequences of failure. It was concluded that UO/sub 2/ and UN fuels show approximately equal performance potential and that UC fuel has lesser po… more

Date: December 1, 1983

Creator: Cox, C.M.; Dutt, D.S. & Karnesky, R.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Program for personnel protection from oxygen deficiency in a Fast Breeder Reactor Test Facility (FFTF)

The FFTF reactor is described. Procedures and equipment used to protect personnel from potential hazards of oxygen deficient environments are described.

Date: December 12, 1979

Creator: Bell, J.C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Packaging and shipment of U. S. breeder reactor experiments

Irradiation testing of fuels and materials in the Fast Test Reactor (FTR) required development of a shipping cask (designated T-3) and associated hardware for loading and shipping of these experiments to postirradiation examination facilities. The T-3 shipping-cask program included design, fabrication, and testing of internal cask packages to protect the experiments during loading, shipping, and unloading. The cask was designed for loading in both the vertical and horizontal attitudes.

Date: January 1, 1980

Creator: Berger, J. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thick Target Neutron Yields and Spectra From the Li(d,xn) Reaction at 35 Mev

Measurements were performed using a 35 MeV deuteron beam from the isochronous cyclotron at the University of California at Davis. Data were obtained using the time-of-flight technique with an NE213 liquid scintillator. One set of measurements was used to observe the neutron spectrum from approx. 1 MeV to approx. 50 MeV, the maximum kinematically allowed energy. Observation angles were from 0/sup 0/ to 150/sup 0/ with emphasis on forward angles. Spectral data below approx. 1.5 MeV had poor accur… more

Date: May 1, 1980

Creator: Johnson, D. L.; Mann, F. M.; Watson, J. W.; Brady, F. P.; Ullmann, J. L.; Romero, J. L. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Computer based training cost-benefit model

The costs of establishing a computer-based training program for FFTF reactor operators are analyzed.

Date: January 1, 1984

Creator: Gardner, P.R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Frank loop unfaulting mechanism in fcc metals during neutron irradiation

The unfaulting mechanism whereby sessile Frank dislocation loops evolve into a complex tangle of glissile dislocations during irradiation of face centered cubic metals is not well understood. It is presumed that such loops grow by absorption of point defects until interactions develop which provide sufficient impetus for nucleation of an unfaulting event. The loops then become glissile, interact and form a dislocation network. An alternate mechanism which has been observed to occur in an austen… more

Date: May 1980

Creator: Gelles, D. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Swelling in several commercial alloys irradiated to very high neutron fluence

Swelling values have been obtained from a set of commercial alloys irradiated in EBR-II to a peak fluence of 2.5 x 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV) or approx. 125 dpa covering the range 400 to 650/sup 0/C. The alloys can be ranked for swelling resistance from highest to lowest as follows: the martensitic and ferritic alloys, the niobium based alloys, the precipitation strengthened iron and nickel based alloys, the molybdenum alloys and the austenitic alloys.

Date: January 1, 1983

Creator: Gelles, D. S. & Pintler, J. S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

FFTF utilization for irradiation testing

FFTF utilization for irradiation testing is beginning. Two Fuels Open Test Assemblies and one Vibration Open Test Assembly, both containing in-core contact instrumentation, are installed in the reactor. These assemblies will be used to confirm plant design performance predictions. Some 100 additional experiments are currently planned to follow these three. This will result in an average core loading of about 50 test assemblies throughout the early FFTF operating cycles.

Date: January 1, 1980

Creator: Corrigan, D. C.; Julyk, L. J.; Hoth, C. W.; McGuire, J. C. & Sloan, W. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Damage analysis and fundamental studies

Separate abstracts were prepared for each of the 10 included sections. (MOW)

Date: February 1, 1982

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fast Flux Test Facility loose-parts monitor

This paper summarizes the development testing in progress at the FFTF to determine the effectiveness of high temperature microphones as acoustic monitors in the upper plenum of the FFTF. The specific goal of this testing is development of an automated loose parts monitor for the upper plenum. A description of the acoustic probe is included, as well as a discussion of the signal processing. A summary of the results to date is also given.

Date: February 1, 1982

Creator: Sloan, W.R.; King, D.C. & Robles, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department