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Distribution of fissionable material in thermal reactors of spherical geometry for uniform power generation

Description: Report presenting a solution for the two-group equations for reflected thermal reactors of spherical geometry for constant power generation over the reactor-core volume. Solution is obtained both analytically and by means of an electrical analogue simulator.
Date: June 1952
Creator: McCready, Robert R.; Spooner, Robert B. & Valerino, Michael F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Some Control Properties of Reflector Moderated Reactors

Description: The current trend in the design of research reactors is toward heavily loaded cores in which most of the neutrons are thermalized in the reflector before returning to the core. These reactors often have control properties quite different than the usual thermal reactors. In this paper some of these properties are examined and it is shown that extreme care must be used in the design of such reactors.
Date: 1962
Creator: Michael, Paul
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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New burnout correlation for annuli

Description: A number of burnout tests have been run subsequent to the publication of the burnout equations in DP-355 and DP-725. The range of variables was extended in these tests and the burnout heat flux was measured. This memorandum presents a modified empirical equation, which correlates the new data, for use in the design of fuel assemblies for the HWCTR. We expect to submit this material for a journal publication within the next quarter.
Date: March 26, 1964
Creator: Towell, R.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal stability of zirconia-s and thoria-base fuels (LWBR Development Program)

Description: Vapor densities and/or dissociation pressures of UO/sub 2/, ThO/sub 2/, ZrO/sub 2/, ThO/sub 2/-8 and -20 wt % UO/sub 2/, and ZrO/sub 2/-20 and -50 wt % UO/sub 2/ were obtained in the range from 2000 to 3000/sup 0/K by the transpiration technique. The UO/sub 2/-ZrO/sub 2/ system exhibited marked positive deviation from ideality, indicative of a strong tendency toward immiscibility. The UO/sub 2/-ThO/sub 2/ system was found to behave almost ideally. On the basis of the vapor pressures of UO/sub 2… more
Date: January 6, 1967
Creator: Alexander, C. A.; Ogden, J. S. & Cunningham, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of fuel rods containing /sup 233/U pelletized oxide fuels (LWBR Development Program)

Description: Approximately 13 kg of U-233 were fabricated into 1 wt % UO/sub 2/-ThO/sub 2/ and 26 wt % UO/sub 2/-ZrO/sub 2/ pellets and enclosed in Zircaloy-2 cladding tubes as 1299 blanket and 377 seed rods. The U-233 contained 38 ppM of U-232, and was purified as two batches of liquid UO/sub 2/(NO/sub 3/)/sub 2/ immediately prior to processing into powder form. All fuel rods were completed within 95 days of this initial solvent extraction of the nitrate. Overall U yield of nitrate to usable materials was … more
Date: February 1967
Creator: Frankhouser, W. L.; Crain, H. H.; Fischer, R. L.; Suldan, J. H.; Eyler, J. H. & Speer, E. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication, characterization, and thermal-property measurements of ThO/sub 2/--UO/sub 2/ fuel materials (LWBR Development Program)

Description: Thermophysical-property specimens of ThO/sub 2/, ThO/sub 2/-10 wt % UO/sub 2/, and ThO/sub 2/-20 wt % UO/sub 2/ were fabricated and characterized. Each material composition was represented by specimens with nominal densities of 95, 85, and 75 percent of theoretical. Thermal-diffusivity, linear-thermal-expansion, and specific-heat measurements were made at 300 to 1900/sup 0/C and used to determine thermal conductivity. Results of linear-thermal-expansion and specific-heat measurements were appro… more
Date: October 1, 1967
Creator: Springer, J. R.; Eldridge, E. A.; Goodyear, M. U.; Wright, T. R. & Lagedrost, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design criteria for an HTGR reference fuel reprocessing plant

Description: Design criteria are given for a conceptual reprocessing plant capable of processing HTGR-type graphite-based fuel. The single-purpose plant is designed to reprocess 260 metric tons of fuel per year consisting of HTGR reference-type and Fort St. Vrain fuel plus a small amount of Peach Bottom fuel. The design incorporates a burn-leach type headend, separate modified Acid-thorex flowsheets for solvent extraction recovery of the heavy metals from both the fertile and fissile particles, and denitrat… more
Date: December 1, 1968
Creator: Modrow, R. D.; Freeby, W. A.; Borduin, L. C.; Kertamus, N. J. & Wheeler, B. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High flux isotope reactor quarterly report, October, November, and December of 1975

Description: Routine operation of the reactor was resumed with an onstream time of 93.7 percent. An in-reactor test of four journal-type bearings on one control plate was started. These bearings will be operated for four fuel cycles, if no problems develop. The use of chromate salts for corrosion protection in the secondary coolant system was discontinued. Basic operating data are presented.
Date: unknown
Creator: McCord, R. V. & Corbett, B. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Methods for calculating group cross sections for doubly heterogeneous thermal reactor systems. [HTGR]

Description: The report discusses methods used at LASL for calculating group cross sections for doubly heterogeneous HTGR systems of the General Atomic design. These cross sections have been used for the neutronic safety analysis calculations of such HTGR systems at various points in reactor lifetime (e.g., beginning-of-life, end-of-equilibrium cycle). They were also compared with supplied General Atomic cross sections generated with General Atomic codes. The overall agreement between the LASL and the GA cr… more
Date: unknown
Creator: Stamatelatos, M. G. & LaBauve, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quasi-static core liquid level depression and long-term core uncovery during a PWR LOCA

Description: The possibility exists that the core liquid level can be depressed quasi-statically during long-term plant cooldown following a cold-leg-break loss-of-coolant accident in a pressurized-water reactor. Such a level depression can take place if the core steaming rate is almost balanced with the steam condensation rate in the reactor coolant system (RCS). Integral experiments simulating three steam condensation modes in the RCS have shown that quasi-static level depressions can happen and thus have… more
Date: unknown
Creator: Kukita, Y.; Nakamura, H. (Japan Atomic Energy Research Institute, Tokai-Mura, Ibaraki-Ken (Japan)); Schultz, R. R. (Idaho National Engineering Lab., Idaho Falls, ID (United States)) & Katayama, J. (Muroran Institute of Technology, Muroran-Shi, Hokkaido (Japan))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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