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in subjects: "Sodium"

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Creep relaxation of fuel pin bending and ovalling stresses

Analytical methods for calculating fuel pin cladding bending and ovalling stresses due to pin bundle-duct mechanical interaction taking into account nonlinear creep are presented. Calculated results are in close agreement with finite element results by MARC-CDC program. The methods are used to investigate the effect of creep on the FTR fuel cladding bending and ovalling stresses. It is concluded that the cladding of 316 SS 20% CW and reference design has high creep rates in the FTR core region … more

Date: June 1, 1979

Creator: Chan, D. P. & Jackson, R. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Improvements in EBR-2 core depletion calculations

The need for accurate core depletion calculations in Experimental Breeder Reactor No. 2 (EBR-2) is discussed. Because of the unique physics characteristics of EBR-2, it is difficult to obtain accurate and computationally efficient multigroup flux predictions. This paper describes the effect of various conventional and higher order schemes for group constant generation and for flux computations; results indicate that higher-order methods are required, particularly in the outer regions (i.e. the … more

Date: January 1, 1991

Creator: Finck, P.J.; Hill, R.N. & Sakamoto, S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

OSCAR experiment high-density network data report: Event 4 - April 21-23, 1981

The OSCAR (Oxidation and Scavenging Characteristics of April Rains) experiment, conducted during April 1981, was a cooperative field investigation of wet removal in cyclonic storm systems. The high-density component of OSCAR was located in northeast Indiana and included sequential precipitation chemistry measurements on a 100 by 100 km netwok, as well as airborne air chemistry and cloud chemistry mueasurements, surface air chemistry measurements, and supporting meteorological measurements. Four… more

Date: December 1, 1984

Creator: Dana, M.T.; Easter, R.C. & Thorp, J.M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

D7 debris-bed experiment. [LMFBR]

The D7 experiment investigated heat removal from a shallow, stratified bed of UO/sub 2/ particulate in sodium. The particle diameters ranged from 0.1 to 1.0 mm, with the largest particles at the bottom. The bed thickness was 74 mm and the average porosity was 41%. The incipient dryout power varied from 0.43 W/g to 0.25 W/g as the sodium subcooling (saturation temperature minus overlying pool temperature) was reduced from 390/sup 0/C to 170/sup 0/C. These powers were only slighlty above the inci… more

Date: August 1, 1983

Creator: Mitchell, G W; Ottinger, C A & Lipinski, R J

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Measurements of astrophysical reaction rates for radioactive samples

Reaction rates for both big-bang and stellar nucleosynthesis can be obtained from the measurement of (n,p) and (n,..gamma..) cross sections for radioactive nuclei. In the past, large backgrounds associated with the sample activity limited these types of measurements to radioisotopes with very long half lives. The advent of the low-energy, high-intensity neutron source at the Los Alamos Neutron Scattering CEnter (LANSCE) has greatly increased the number of nuclei which can be studied. Results of… more

Date: January 1, 1987

Creator: Koehler, P. E.; O'Brien, H. A. & Bowman, C. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Feedback components of a U20Pu10Zr-fueled compared to a U10Zr-fueled EBR-II

Calculated feedback components of the regional contributions of the power reactivity decrements (PRDs) and of the temperature coefficients of reactivity of a U20Pu10Zr-fueled and of a U10Zr-fueled Experimental Breeder Reactor II (EBR-II) are compared. The PRD components are also separated into power-to-flow dependent and solely power dependent parts. The effects of these values upon quantities useful for indicating the comparative potential inherent safety characteristics of these EBR-II loadin… more

Date: January 1, 1988

Creator: Meneghetti, D. & Kucera, D.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Status of development and licensing support for advanced liquid metal reactors in the United States

The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the ALMR plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the US program is to produce a standard, commercial ALMR, including the associated fuel cycle. The paper addresses the status of the IFR program, the ALMR… more

Date: January 1, 1991

Creator: Pedersen, D.R. (Argonne National Lab., IL (United States)) & Gyorey, G. (General Electric Co., San Jose, CA (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Core concepts for zero-sodium-void-worth core'' in metal fuelled fast reactor

Core design options to reduce the sodium void worth in metal fueled LMRs are investigated. Two core designs which achieve a zero sodium void worth are analyzed in detail. The first design is a pancaked'' and annular core with enhanced transuranic burning capabilities; the high leakage in this design yields a low breeding ratio and small void worth. The second design is an axially multilayered annular core which is fissile self-sufficient; in this design, the upper and lower core regions are neu… more

Date: January 1, 1991

Creator: Chang, Y. I.; Hill, R. N.; Fujita, E. K.; Wade, D. C. (Argonne National Lab., IL (United States)); Kumaoka, Y.; Suzuki, M. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Simulation experiments for a large leak sodium-water reaction analysis. Volume 4. IHTS/relief system simulation tests

Tests were performed in which a simplified 1/8-scale model of the intermediate heat transfer system and relief system of a LMFBR was subjected to a simulated sodium-water reaction in a steam generator. Pressures in the intermediate heat exchanger (IHX) and in the pipe were measured. The flow of water through the relief system was photographed and its velocity was measured. The forces on the relief system elbows resulting from the fluid flow were also measured. The tests were performed primarily… more

Date: September 1978

Creator: Ploeger, D.W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Fuel pin failure in the PFR/TREAT experiments

The PFR/TREAT safety testing programme involves the transient testing of fresh and pre-irradiated UK and US fuel pins. This paper summarizes the experimental and calculational results obtained to date on fuel pin failure during transient overpower (resulting from an accidental addition of resolivity) and transient undercooling followed by overpower (arising from an accidental stoppage of the primary sodium circulating pumps) accidents. Companion papers at this conference address: (I) the progre… more

Date: January 1, 1986

Creator: Herbert, R.; Hunter, C. W.; Kramer, J. M.; Wood, M. H. & Wright, A. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Automated start-up of EBR-II: A preview

Oak Ridge National Laboratory (ORNL) and Argonne National Laboratory (ANL) are undertaking a joint project to develop control philosophies, strategies, and algorithms for computer control of the start-up mode of the Experimental Breeder Reactor II (EBR-II). The major objective of this project is to show that advanced liquid-metal reactor (LMR) plants can be operated from low power to full power using computer control. Development of an automated control system with this objective in view will h… more

Date: January 1, 1989

Creator: Kisner, R. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Criticality experiments with fast flux test facility fuel pins

A United States Department of Energy program was initiated during the early seventies at the Hanford Critical Mass Laboratory to obtain experimental criticality data in support of the Liquid Metal Fast Breeder Reactor Program. The criticality experiments program was to provide basic physics data for clean well defined conditions expected to be encountered in the handling of plutonium-uranium fuel mixtures outside reactors. One task of this criticality experiments program was concerned with obta… more

Date: November 1, 1990

Creator: Bierman, S.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Plant inherent control testing in EBR-II

Recent tests in the Experimental Breeder Reactor II (EBR-II) have demonstrated that reactor feedbacks can passively reduce power and thus effectively mitigate reactor undercooling caused by equipment failures. A follow-on testing program is being designed to investigate the use of these feedbacks along other liquid metal reactor (LMR) characteristics to routinely control reactor power during plant maneuvers and fuel burnup, compensation, and to limit the possibility and consequences of over-pow… more

Date: January 1, 1987

Creator: Chang, L.K.; Mohr, D.; Feldman, E.E. & Planchon, H.P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

OSCAR experiment high-density network data report: Event 1 - April 8-9, 1981

The OSCAR (Oxidation and Scavenging Characteristics of April Rains) experiment, conducted during April 1981, was a cooperative field investigation of wet removal in cyclonic storm systems. The high-densiy component of OSCAR was located in northeast Indiana and included sequential precipitation chemistry measurements on a 100 by 100 km network, as well as airborne air chemistry and cloud chemistry measurements, surface air chemistry measurements, and supporting meteorological measurements. Four … more

Date: December 1, 1984

Creator: Dana, M.T.; Easter, R.C. & Thorp, J.M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Surveillance application using patten recognition software at the EBR-II Reactor Facility

The System State Analyzer (SSA) is a software based pattern recognition system. For the past several year this system has been used at Argonne National Laboratory's Experimental Breeder Reactor 2 (EBR-2) reactor for detection of degradation and other abnormalities in plant systems. Currently there are two versions of the SSA being used at EBR-2. One version of SSA is used for daily surveillance and trending of the reactor delta-T and startups of the reactor. Another version of the SSA is the QS… more

Date: January 1, 1992

Creator: Olson, D.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Application of high fluence fast reactor data to fusion-relevant materials problems

In three recent comparative studies in HFIR and EBR-II where the effect of helium and solid transmutants could be assessed, it was found that in each case there was no significant perturbation of the macroscopic property change under consideration. These findings reinforce the belief that fast reactors can serve as a major tool for fusion materials studies and that the effects of helium and other transmutants can be treated as second-order perturbations to be studied by other methods. A number … more

Date: May 1, 1985

Creator: Garner, F.A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Experience with model based display for advanced diagnostics and control

A full color, model based display system based on the Rankine thermodynamic cycle has been developed for use at the Experimental Breeder Reactor II by plant operators, engineers, and experimenters. The displays generate a real time thermodynamic model of the plant processes on computer screens to provide a direct indication of the plant performance. Operators and others who view the displays are no longer required to mentally ''construct'' a model of the process before acting. The model based d… more

Date: January 1, 1989

Creator: Staffon, J. D. & Lindsay, R. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Comparative evaluation of liner materials for inactive uranium-mill-tailings piles

Under the funding of the Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Program, Pacific Northwest Laboratory (PNL) has completed the initial accelerated testing phase of eight candidate liner materials. The tests were designed to comparatively evaluate the long term effectiveness of liner materials as a radionuclide and hazardous chemical leachate barrier. The eight materials tested were selected from a technical review of published literature and industrial specialists. … more

Date: January 1, 1981

Creator: Buelt, J. L. & Barnes, S. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Validation of a PC based program for single stage absorption heat pump

An interactive computer code was developed to evaluate single stage absorption heat pump performance for temperature amplifier and heat amplifier modes using water as the refrigerant. This program performs the cycle calculations for single stage cycles based on the polynomial expressions developed to correlate experimental vapor-liquid-equilibrium (VLE) and specific enthalpy-concentration data for LiBr/water and (Li, K, Na)NO{sub 3}/water systems as well as the properties of pure water. The ope… more

Date: September 1, 1991

Creator: Zaltash, A. & Ally, M.R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Off-normal performance of EBR-II (Experimental Breeder Reactor) driver fuel

The off-normal performance of EBR-II Mark-II driver fuel has been more than satisfactory as demonstrated by robust reliability under repeated transient overpower and undercooled loss-of-flow tests, by benign run-beyond-cladding-breach behavior, and by forgiving response to fabrication defects including lack of bond. Test results have verified that the metallic driver fuel is very tolerant of off-normal events. This behavior has allowed EBR-II to operate in a combined steady-state and transient … more

Date: September 1, 1986

Creator: Seidel, B.R.; Batte, G.L.; Lahm, C.E.; Fryer, R.M.; Koenig, J.F. & Hofman, G.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fluence, dosimetry, and steel-dpa rates in EBR-II

Sensitivities of steel displacements-per-atom (dpa) rates to fluence-rate spectra in regions of th Experimental Breeder Reactor II (EBR-II) are presented. Low sensitivities in EBR-II of ratios of dpa-to-fission rates assuming /sup 240/Pu as a dosimeter suggests its possible use for adjusting calculated dpa-rates for effects of errors in calculated fluence-spectra. Extension of the method to outer regions, having more degraded spectra, by use of /sup 10/B-shielded /sup 240/Pu dosimeters is also … more

Date: January 1, 1984

Creator: Meneghetti, D. & Kucera, D.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Distribution of metal and adsorbed guest species in zeolites

Because of their high internal surface areas and molecular-size cavity dimensions, zeolites are used widely as catalysts, shape- selective supports, or adsorbents in a variety of important chemical processes. For metal-catalyzed reactions, active metal species must be dispersed to sites within the zeolite pores that are accessible to diffusing reactant molecules. The distribution of the metal, together with transport and adsorption of reactant molecules in zeolite powders, are crucial to ultima… more

Date: December 1, 1989

Creator: Chmelka, B.F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Thermal-hydraulic impact of failure of highly irradiated fuel pins on LMR passive safety

The EBR-2 SHRT-45 loss-of-primary-flow-without scram test and SHRT 302 unprotected loss-of-heat-sink test have demonstrated that liquid metal reactors can be built with a high degree of passive safety. No fuel pins were observed to fail in these tests; but if the burnup of the fuel were pushed further, one would face the question of what could be the impact of pin failures and rapid release of plenum gas in such a transient. Also, there are questions about the impact of an unprotected rapid rel… more

Date: January 1, 1990

Creator: Dunn, F.E. & Herzog, J.P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Loading and leakage of krypton immobilized in zeolites and glass

Krypton-85 is formed in nuclear power reactors and remains trapped until the fuel is reprocessed. Federal regulations limit the release of /sup 85/Kr to the environment, requiring recovery and storage of 85% of the /sup 85/Kr produced in commercial light-water reactors after January 1, 1983. One of the long-term storage options involves encapsulating /sup 85/Kr in zeolites or glasses at high pressure and temperature. This paper presents experimental results for krypton encapsulation and leakage… more

Date: January 1, 1980

Creator: Christensen, A. B.; Del Debbio, J. A.; Knecht, D. A. & Tanner, J. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department