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Development of Advanced LMFBR Fuels.

Description: The goals of this program are to investigate the properties and behavior of those U- and Pu-based ceramic fuels that we term conductors such as the mononitrides, carbonitrides, ad monocarbides - and to compare their potential as liquid-metal fast breeder feactor (LMFBR) fuel with tha of (U,Pu)O2, which by comparison is an insulator.
Date: October 31, 1971
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Equation of state and transport properties of uranium and plutonium nitrides in the liquid region

Description: By the use of available low-temperature data for various thermophysical and transport properties for uranium and plutonium nitrides, values above the melting point of density, heat capacity, enthalpy, vapor pressure, thermal conductivity, and viscosity were estimated. Sets of recommended values have been prepared for the compounds UN, PuN, and (U/sub 0/./sub 8/Pu/sub 0/./sub 2/)N.
Date: October 1, 1976
Creator: Sheth, A. & Leibowitz, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutronic performance of high-density LEU fuels in water-moderated and water-reflected research reactors

Description: At the Reduced Enrichment for Research and Test Reactors (RERTR) meeting in September 1994, Durand reported that the maximum uranium loading attainable with U{sub 3}Si{sub 2} fuel is about 6.0 g U/cm{sup 3}. The French Commissariat a l`Energie Atomique (CEA) plan to perform irradiation tests with 5 plates at this loading. Compagnie pour L`Etude et La Realisation de Combustibles Atomiques (CERCA) has also fabricated a few uranium nitride (UN) plates with a uranium density in the fuel meat of 7.0… more
Date: September 1, 1996
Creator: Bretscher, M.M. & Matos, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear and thermal analysis of the heatpipe power and bimodal systems

Description: This paper discusses the nuclear and thermal analysis of two fission-powered concepts: (1)the Heatpipe Power System(HBS), which provides which provides power only, and (2) the Heatpipe Bimodal System (HBS), which provides both power and thermal propulsion. The HPS and HBS systems can provide substantial levels of power and propulsion at low mass with a high degree of safety and reliability. The systems have been designed to utilize existing technology and facilities, which will make the develop… more
Date: December 1, 1995
Creator: Poston, D.I. & Houts, M.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SPR-8 multi-mega watt space power system (MMW-SPS) concept description and concept refinement plan

Description: The SPR-8 MMW-SPS concept can satisfy both continuous and burst mode power requirements. At 10 MWe continuous mode power for 5 yr and 75 MWe burst mode power for 200 sec, the SPR-8 concept can power radar systems for detecting ballistic missile launchings and for discriminating between warheads and decoys. When enemy action is detected the SPR-8 MMW-SPS can power a rail gun, free electron laser, or particle beam and destroy the missile in the boost phase or warheads in space flight. The SPR-8 c… more
Date: April 15, 1985
Creator: Walter, C.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During February 1958

Description: The creep properties of 16% cold-worked Zircaloy-2 are being evaluated over the 232 to 299 deg C temperature range. helium density measurements were made on samples of UO/sub 2/, and the results are tabulated. Phase boundaries in the Zr--1 wt.% U alloy system were studied. Results of 168-hr corrosion testing of U--Nb and U--Mo alloys in 680 deg F water are given. The reaction between U and water or water vapor is being studied at temperatures ranging up to 200 deg C. Data are given on the hardn… more
Date: March 1, 1958
Creator: Dayton, R. W. & Tipton, C. R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hot-pressing study on mixed uranium--plutonium nitride for advanced reactor fuel

Description: The hot-pressing characteristics of mixed (U,Pu)N for advanced reactor fuel were studied in order to provide a better insight into the densification process and thus improve fuel fabrication technique. A detailed experimental procedure for continuous measurement of densification and an analog computer circuit to simulate hot-pressing are presented. Mixed (U,Pu)N of 99 percent density was fabricated at 4000 psi and 1450$sup 0$C, and 94 percent density was obtained with 3000 psi at 1450$sup 0$C. … more
Date: November 1, 1975
Creator: Chang, J.Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SP-100 fuel pin performance: Results from irradiation testing

Description: A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pin are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-re… more
Date: September 1, 1993
Creator: Makenas, B. J.; Paxton, D. M.; Vaidyanathan, S. & Hoth, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Phonon dispersion relation of uranium nitrate above and below the Neel temperature

Description: Neutron coherent inelastic scattering measurements have been made of the phonon dispersion relation of uranium nitride both above and below the Neel temperature T/sub N/ = 50 K. Within the precision of the measurements, about 1% in frequency and 10% in line width and in scattered neutron intensity, no significant changes in these phonon properties were observed as a function of temperature other than those arising from population factor changes and a small stiffening of the lattice as the tempe… more
Date: January 1, 1977
Creator: Dolling, G; Holden, T M; Evensson, E C; Buyers, W J.L. & Lander, G H
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Photoelectron spectra of actinide compounds

Description: A brief overview of the application of photoelectron spectroscopy is presented for the study of actinide materials. Phenomenology as well as specific materials are discussed with illustrative examples. (FS)
Date: January 1, 1979
Creator: Veal, B.W. & Lam, D.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During December 1960

Description: Research areas include: reactor materials and components; alloy fuels; fission-gas release from refractory fuels; fuel-element development; gas-pressure bonding of ceramic, cermet, and dispersion fuel elements; development of uranium carbide; physical research; radioisotope and radiation applications; void- distribution and heattransfer studies; development of uranium mononitride; materials development and evaluation; coated-particle fuel materials; problems associated with recovery of spent fu… more
Date: January 1, 1961
Creator: Dayton, R. W. & Tipton, C. R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ZPPR-20 Phase D : A Cylindrical Assembly of Polyethylene Moderated U Metal Reflected by Beryllium Oxide and Polyethylene.

Description: The Zero Power Physics Reactor (ZPPR) fast critical facility was built at the Argonne National Laboratory-West (ANL-W) site in Idaho in 1969 to obtain neutron physics information necessary for the design of fast breeder reactors. The ZPPR-20D Benchmark Assembly was part of a series of cores built in Assembly 20 (References 1 through 3) of the ZPPR facility to provide data for developing a nuclear power source for space applications (SP-100). The assemblies were beryllium oxide reflected and had… more
Date: September 30, 2006
Creator: Lell, R.; Grimm, K.; McKnight, R.; Shaefer, R.; Division, Nuclear Engineering & INL
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status of the SNAP-50 reactor fuels parametric studies. Part I

Description: Declassified 6 Sep 1973. Results of the parametric study are given for both present and advanced capability (2 and 8 MW). Fuels which result in minimum reactor weights are UC/UN (95% dense), UC/UN--1W for the 2 MW design, UC/ UN-1W for 8 MW. Effects of fuel clad and fuel maximum temperature on the reactor weight were also studied. Recommendations are made for the 2-MW SNAP-50/ SPUR fuel element development and reactor design program, and for additional parametric studies. (DLC)
Date: March 1, 1964
Creator: Banach, H.B. & Richings, H.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status of uranium nitride development program at the Oak Ridge National Laboratory. Part II

Description: From RDT/SNS meeting on materials development for space reactor power systems; Washington, D. C. (23 Apr 1968). Declassified 26 Nov 1973. Information is included on encapsulated UN irradiation testing in the Materials Testing Reactor, results of post-irradiation evaluation of UN capsules, and irradiation testing of clad UN fuel pins in the Low Intensity Test Reactor and in the Oak Ridge Research Reactor. (JRD)
Date: April 30, 1974
Creator: Weaver, S.C. & Scott, J.L. (comps.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Studies of Sintered Refractory Uranium Compounds

Description: The refractory uranium compounds UC and UC/sub 2/ were prepared by arc- melting methods, UN by gas solid reactions, and UB/sub 2/ and UBe/aub 13/ by solid-solid reactions. Techniques for sintering powder compacts of these compounds to densities 90% of theoretical or greater were developed. Mean linear thermal-expansion coefficients of 7.9 x 10/sup -6/ per deg F for Uc and 9.3 x 1O/ sup -6/ per deg F for UBe/sub 13/ were obtained in the range 68 to 1800 deg F. The thermal conductivity of sintere… more
Date: January 27, 1959
Creator: Tripler, A. B., Jr.; Snyder, M. J. & Duckworth, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of diffusion barrier technology for application in SP-100 fuel pins

Description: The fuel pin design for the SP-100 reactor uses uranium nitride fuel contained in a niobium alloy (Nb-1Zr) cladding. Chemical reactions occur between the fuel and the cladding at the planned operating temperatures of 1350 to 1500 K, so a diffusion barrier is required to prevent degradation. The technology associated with diffusion barriers in similar fuel pins is reviewed to identify fabrication techniques and to summarize previous results of chemical compatibility and irradiation tests. Four f… more
Date: August 1, 1987
Creator: Schmidt, M. A. & Kania, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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