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Some Scoping Experiments for a Space Reactor

Description: Some scoping experiments were performed to evaluate fuel performance in a lithium heat pipe reactor operating at a nominal 1500K heat pipe temperature. Fuel-coolant and fuel-coolant-clad relationships showed that once a failed heat pipe occurs temperatures can rise high enough so that large concentrations of uranium can be transported by the vapor phase. Upon condensation this uranium would be capable of penetrating heat pipes adjacent to the failed pipe. The potential for propagation of failur… more
Date: July 7, 1983
Creator: Alexander, C. A. & Ogden, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High performance, suppressed-fission ICF hybrid

Description: The neutronics aspects of an ICF hybrid concept are discussed. The breeding blanket consists of a beryllium neutron multiplier, metallic thorium fertile fuel and a liquid-lithium coolant. The fertile fuel fraction is 30 vol%, which is much higher than previous one-zone, suppressed-fission hybrid concepts. Fission in the bred /sup 233/U is suppressed by competition from tritium breeding reactions in /sup 6/Li. The total breeding ratio, T + F, is 2.05, and the total neutron energy deposited is 41… more
Date: December 1, 1983
Creator: Meier, W. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparative analysis of internal fuel motion in annular fuel designs

Description: 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: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fuel systems for compact fast space reactors

Description: 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: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Preliminary analysis of fission gas behavior and fuel response during an LMFBR operational transient

Description: This summary presents results obtained from a preliminary analysis of gas behavior and oxide fuel response during an LMFBR operational transient. The DiMelfi and Deitrich model is extrapolated to operational transient regimes to delineate brittle versus ductile fuel response modes. All pertinent parameters necessary for application of the DiMelfi and Deitrich model were obtained from the LIFE-3 code.
Date: January 1, 1983
Creator: Liu, Y. Y.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reactor safety research programs. Quarterly report, April-June 1983. Vol. 2

Description: This document summarizes work performed by Pacific Northwest Laboratory from April 1 through June 30, 1983, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth i… more
Date: December 1, 1983
Creator: Edler, S.K. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Blanket comparison and selection study. Volume II

Description: This volume contains extensive data for the following chapters: (1) solid breeder tritium recovery, (2) solid breeder blanket designs, (3) alternate blanket concept screening, and (4) safety analysis. The following appendices are also included: (1) blanket design guidelines, (2) power conversion systems, (3) helium-cooled, vanadium alloy structure blanket design, (4) high wall loading study, and (5) molten salt safety studies. (MOW)
Date: October 1, 1983
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Post-test examination observations for the W-2 SLSF experiment. [Sodium Loop Safety Facility]

Description: Gamma scanning measurements revealed that the axial power profile in these test trains was more peaked than expected based on pretest calculations and critical facility measurements. These results implied that the thermal flux incident on the test assembly was greater than expected, which was manifested in highly skewed and extensive fuel melting zones in the outer pin fuel pellets. Observations indicated that the extent of fuel melting near the midplane exceeded 90% of the pellet radius in som… more
Date: September 1, 1983
Creator: Pitner, A. L.; Smith, D. E. & Culley, G. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Temperature dependence of the damage microstructures in neutron-irradiated vanadium

Description: Vanadium and vanadium with boron carbide additions (V-B/sub 4/C) were irradiated to approx. 1 dpa in the Oak Ridge Research Reactor at controlled temperatures ranging from 455 to 925 K. The V-B/sub 4/C alloy was enriched in /sup 10/B, which produced approx. 3900 at. ppM helium. In the vanadium specimens, the dislocation microstructures varied from clusters of small (< 50 nm diam) dislocation loops (455 to 625 K) to larger, homogeneously distributed loops at higher temperatures. Their Burgers ve… more
Date: January 1, 1983
Creator: Horton, L. L. & Farrell, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of the U/sub 3/O/sub 8/-Al thermite reaction and strength of reactor fuel tubes

Description: Research and test reactors are presently operated with aluminum-clad fuel elements containing highly enriched uranium-aluminum alloy cores. To lower the enrichment and still maintain reactivity, the uranium content of the fuel element will need to be higher than currently achievable with alloy fuels. This will necessitate conversion to other forms such as U/sub 3/O/sub 8/-aluminum cermets. Above the aluminum melting point, U/sub 3/O/sub 8/ and aluminum undergo an exothermic thermite reaction an… more
Date: January 1, 1983
Creator: Peacock, H B
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

Description: The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the react… more
Date: December 1, 1983
Creator: Cover, L.E.; Bohn, M.P.; Campbell, R.D. & Wesley, D.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control rod trip failures. Salem 1: the cause, response and potential fixes

Description: Although the failure to trip or scram represents a single class of initiators, the actual events of each transient are operationally unique and require individual human response. The operational team's reaction to the challenge can be successful, in very short response times, and without complete diagnosis of the event's root cause. This underscores the need for a better basic understanding of the team response patterns in such cases, to allow designs, procedures, and training to take advantage… more
Date: January 1, 1983
Creator: Hall, R.E.; Boccio, J.L. & Luckas, W.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TRAC analysis and support of Oconee-1 PTS studies. [Pressurized thermal shock following overcooling transients]

Description: This paper describes the overall pressurized thermal shock (PTS) program at Los Alamos with emphasis on TRAC-PF1 calculations of severe overcooling transients for the Oconee-1 pressurized water reactor (PWR). A summary of results for several calculations are presented for the Oconee-1 PWR along with detailed discussions of two of the most severe overcooling transients predicted (main steam-line break and turbine-bypass valve (TBV) failures). The calculations performed were plant specific in tha… more
Date: January 1, 1983
Creator: Ireland, J.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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FELIX: construction and testing of a facility to study electromagnetic effects for first wall, blanket, and shield systems

Description: An experimental test facility for the study of electromagnetic effects in the FWBS systems of fusion reactors has been constructed over the past 1-1/2 years at Argonne National Laboratory (ANL). In a test volume of 0.76 m/sup 3/ a vertical pulsed 0.5 T dipole field (B < 50 T/s) is perpendicular to a 1 T solenoid field. Power supplies of 2.75 MW and 5.5 MW and a solid state switch rated 13 kV, 13.1 kA (170 MW) control the pulsed magnetic fields. The total stored energy in the coils is 2.13 MJ. T… more
Date: January 1, 1983
Creator: Praeg, W. F.; Turner, L. R.; Biggs, J. A.; Knott, M. J.; Lari, R. J.; McGhee, D. G. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparison of the Aerospace Systems Test Reactor loss-of-coolant test data with predictions of the 3D-AIRLOCA code

Description: This paper compares the predictions of the revised 3D-AIRLOCA computer code to those data available from the Aerospace Systems Test Reactor's (ASTR's) loss-of-coolant-accident (LOCA) tests run in 1964. The theoretical and experimental hot-spot temperature responses compare remarkably well. In the thirteen cases studied, the irradiation powers varied from 0.4 to 8.87 MW; the irradiation times were 300, 1540, 1800, and 10/sup 4/ s. The degrees of agreement between the data and predictions provide… more
Date: January 1, 1983
Creator: Warinner, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Seismic design technology for breeder reactor structures. Volume 4. Special topics in piping and equipment

Description: This volume is divided into five chapters: experimental verification of piping systems, analytical verification of piping restraint systems, seismic analysis techniques for piping systems with multisupport input, development of floor spectra from input response spectra, and seismic analysis procedures for in-core components. (DLC)
Date: April 1, 1983
Creator: Reddy, D.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tandem mirror technology demonstration facility

Description: This report describes a facility for generating engineering data on the nuclear technologies needed to build an engineering test reactor (ETR). The facility, based on a tandem mirror operating in the Kelley mode, could be used to produce a high neutron flux (1.4 MW/M/sup 2/) on an 8-m/sup 2/ test area for testing fusion blankets. Runs of more than 100 h, with an average availability of 30%, would produce a fluence of 5 mW/yr/m/sup 2/ and give the necessary experience for successful operation of… more
Date: October 1, 1983
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pressure drop considerations of a lithium cooled fusion breeder tokamak reactor blanket

Description: Liquid lithium was selected as one of the coolants for the 1983 fusion breeder blanket used on the magnetically confined tokamak fusion reactor, and as a result, the thermal-hydraulic calculations were dominated by magnetohydrodynamic (MHD) considerations. The applicable sets of MHD equations for the engineering thermal-hydraulic design were reviewed and compared. Special attention was given to the MHD calculations for the fertile material zone, a packed bed of composite beryllium and thorium b… more
Date: December 6, 1983
Creator: Wong, C. P. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Behavior of mixed-oxide fuel subjected to multiple thermal transients

Description: The microstructural behavior of irradiated mixed-oxide fuel subjected to multiple, mild thermal transients was investigated using direct electrical heating. The results demonstrate that significant intergranular porosity, accompanied by large-scale (>90%) release of the retained fission gas, developed as a result of the cyclic heating. Microstructural examination of the fuel indicated that thermal-shock-induced cracking of the fuel contributed significantly to the increased swelling and gas rel… more
Date: November 1, 1983
Creator: Fenske, G.R.; Hofman, G.L.; Neimark, L.A. & Poeppel, R.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Accounting for Time Dependent Source Variations in Surveillance Dosimetry Analysis

Description: One of the difficulties encountered in the calculation of dosimetry reaction rates is how to account for the time dependent behavior of the core source during the irradiation period. Indeed, even the obtaining of this source time dependence in adequate detail is not a trivial task. The straightforward approach of performing a DOT4 or similar transport calculation for each new relative source distribution, although correct, might be prohibitively expensive and time consuming when the irradiation… more
Date: January 1, 1983
Creator: Maerker, R.E. & Williams, M.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterizing W-2 SLSF experiment temperature oscillations using computer graphics. [Sodium Loop Safety Facility]

Description: The W-2 SLSF (Sodium Loop Safety Facility) experiment was an instrumented in-reactor test performed to characterize the failure response of full-length, preconditioned LMFBR prototypic fuel pins to slow transient overpower (TOP) conditions. Although the test results were expected to confirm analytical predictions of upper level failure and fuel expulsion, an axial midplane failure was experienced. Extensive post-test analyses were conducted to understand all of the unexpected behavior in the ex… more
Date: June 23, 1983
Creator: Smith, D. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Acoustic leak detection and ultrasonic crack detection

Description: A program is under way to assess the effectiveness of current and proposed techniques for acoustic leak detection (ALD) in reactor coolant systems. An ALD facility has been constructed and tests have begun on five laboratory-grown cracks (three fatigue and two thermal-fatigue and two field-induced IGSCC specimens. After ultrasonic testing revealed cracks in the Georgia Power Co. HATCH-1 BWR recirculation header, the utility installed an ALD system. Data from HATCH-1 have given an indication of … more
Date: October 1, 1983
Creator: Kupperman, D.S.; Claytor, T.N. & Groenwald, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Extended life aluminide fuel for university research reactors

Description: A test program is being conducted to determine if the fuel loading and burnup limits for fuel elements in university research reactors can be safely increased beyond the limits presently allowed by reactor licensing restrictions. For the tests, 30 fuel plates were constructed to a maximum fuel loading which could be produced on a commercial basis and to contain a maximum boron content as used in the INEL Advanced Test Reactor to reduce initial reactor reactivity. A UAl/sub 2/ fuel matrix was us… more
Date: December 1983
Creator: Miller, Lowell G.; Brown, Keith R.; Beeston, Joseph M. & McGinty, Dave M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Xenon changes under power-burst conditions. [BWR]

Description: Under ordinary operating conditions the xenon concentration in a reactor core can change significantly in times on the order of hours. Core transients of safety significance are much more rapid and hence calculations are done with xenon concentration held constant. However, in certain transients (such as reactivity initiated accidents) there is a very large power surge and the question arises as to whether under these circumstances the xenon concentration could change. This would be particularl… more
Date: January 1, 1983
Creator: Diamond, D. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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