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C-Reactor graphite burnout interim report, 1P-25A(PT-105-532-E)

Description: The oxidation of graphite in the Hanford reactors is of consequence since graphite burnout affects the strength of the moderator. As a means for indication of any highly oxidizing condition within the stack, containers or boats of small weighed samples of reactor-grade graphite are positioned along the length of an empty process channel in each reactor. The rate of oxidation of the monitoring samples, referred to as the burnout rate, is reported as percent weight lose per 1000 operating days (%… more
Date: April 5, 1961
Creator: Ryan, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CONCEPTUAL DESIGN OF A VAPOR VOLUME FRACTION INSTRUMENT

Description: The preliminary design is described of equipment to carry out experiments on boiling burnout in which the average coolant density as a function of coolant channel length as well as local coolant densities may be measured. It appears that by use of the equipment, average densities can be accomplished in a few seconds, while determination of a complete density map (with 5% error) across a plane of the assembly requires approximately one hour. (J.R.D.)
Date: April 5, 1961
Creator: Kalos, M. H.; Davis, S. A.; Mittelman, P. S. & Mastras, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Definition of Tory II-C

Description: From time to time, in discussion of possible naval-based nuclear ramjet missile systems, a question arises concerning whether or not a particular reactor would or would fall within the `Tory II-C Technology`. Such a question is meaningless unless a definition is furnished. This report provides such a definition.
Date: September 5, 1962
Creator: Hadley, J. W. & Reynolds, H. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of production test IP-423-A-FP evaluation of uranium fuel cores having virus heat treatments

Description: Fuel element warp occurring during the irradiation period is considered to be one of the major fuel element dimensional stability problems. Warp has been shown to correlate with accelerated corrosion attack. and also can contribute to stuck fuel charges, particularly in bumpered or self-supported charges where the annular clearances are reduced due to the presence of the projection rails. Thus, any process which offers a potential for reducing the average warp should be evaluated. Preliminary t… more
Date: January 5, 1962
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development Test IP-556-D, supplement A, irradiation service request HAPO-278 outgassing rate of tritium at high temperature

Description: The nuclear heat generation rate in the first capsule irradiated was higher by a factor of two than was calculated. The original capsule was irradiated in a dry bore with cooling water in the annulus only. The new capsule will be irradiated in a water-cooled bore facility with additional cooling coils around the lithium containing tube. This will keep the inner capsule temperature below 150 C during the initial tritium buildup period prior to outgassing. This Supplement authorizes the irradiati… more
Date: July 5, 1963
Creator: DeMers, A. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Douglas United Nuclear, Inc. Report of the working committee to the Fuel Element Development Committee for activities associated with the small and K Hanford Reactors

Description: Currently the B, C, KE and KW reactors are in operation. The B and C reactors are operating to produce 12% Pu-240 in both the E metal (0.95) and natural loadings. Some columns will be taken to 15% Pu 240 on a test basis. Production of 12% Pu-240 will result in exposures of 1400 MWD/ton on natural metal and 2,000 MWD/Ton on E metal. Currently exposures are such that 10 1/2% Pu-240 has been achieved. Some control problems and temperature cycling have been encountered with this mode of operation. … more
Date: September 5, 1967
Creator: Stringer, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effective Specific Impulse of a Pulsed Rocket Engine

Description: The specific impulse achieved in a pulsed rocket engine augmented with a fissioning nuclear bomb could be greater than that of any continuous flow engine. To a certain extent, this increase in specific impulse would be obtained at the expense of motor weight and average thrust. This paper considers the first of these limitations, motor weight, and estimates the highest effective specific impulse to be expected from a nuclear-pulsed rocket motor with respect to the weight of the motor.
Date: May 5, 1965
Creator: Platt, E. A. & Hanner, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of hot die sized Diffusion Bonded Fuel Elements for Supplement ``A`` to Production Test IP-546-A

Description: Production Test IP-546-A. consisting of 20 charges for the purpose of irradiating the first hot die sized fuel elements was charged in C-Reactor July 27, 1963. A second tests PT-IP-616-A containing a total of 19 charges had been charged on two separate outages; 13 land 6 tubes on September 28, 1963 and October 30, 1963, respectively. Fabrication of test quantities was becoming more routine and additional irradiation tests were planned. This report summarizes the fabrication of hot die sized fue… more
Date: October 5, 1964
Creator: Strand, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST FLUX TEST FACILITY CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE HEATING AND VENTILATION SYSTEM NO. 25

Description: The Heating and Ventilation System provides the atmospheric conditions in FFTF as required to assure that plant objectives can be met in a safe and practical manner. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.
Date: December 5, 1969
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST FLUX TEST FACILITY CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE RADIOACTIVE WASTE SYSTEM No. 24

Description: The FFTF Radioactive Waste System provides the equipment and facilities required for the routine collection, transfer, storage, and disposal of radioactive liquid and solid wastes. Radioactive solid wastes and radioactive liquid wastes not normally piped t o the Radioactive Waste System Receiving tanks, are packaged inappropriate containers by the systems generating the waste for collection and disposal by the Radioactive Waste System. Included are functions and design requirements, a physical … more
Date: December 5, 1968
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GETR graphite irradiation capsules: H-4, 5, 6 equivalent N Reactor exposure

Description: A program for the irradiation of samples-of N-Reactor graphite has been in progress since November 30 1961, in the General Electric Test Reactor (GETR). The basic purpose of the program is to achieve an exposure to the samples equivalent to 20 years of operation of N-Reactor and to relate the physical distortion of the samples to the expected behavior of the N-Reactor moderator stack. Theoretical studies to relate sample exposure in the GETR to exposure in N-Reactor have been underway since the… more
Date: March 5, 1964
Creator: Helm, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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H4LM Graphite

Description: A commercial graphite useful in nuclear reactor construction is described. A survey of all currently available sources on chemical and physical properties was made and the information listed. Some data on cost and available sizes are also included. (auth)
Date: July 5, 1962
Creator: Merryman, R. G.; Wagner, P. & MacMillan, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Half plant activated alumina test: Final report

Description: A half reactor test was initiated at B Reactor on February 1, 1967, to determine whether the concentration of P{sup 32} and As{sup 76} in the reactor effluent water would be reduced by the addition of activated alumina in the water treatment process. This test was prompted by the reported effectiveness of activated alumina in sorption of phosphates when water flow is through a packed bed of this material. Although direct feed of material would not be expected to be as effective, testing of this… more
Date: May 5, 1967
Creator: Pitman, R.W. & Wells, G.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford contribution for the eighteenth high temperature fuels committee meeting, May 19--21, 1964

Description: Metallic thorium uranium fuel elements continue to show excellent irradiation performance in high temperature pressurized water coolant. Volume expansion measurements made after 2.1{times}10{sup 20} fissions/cm{sup 3} (6200 MWD/T) at fuel temperatures above 500 C shows no indication of fission gas-in-duced swelling. Analysis of fuel swelling data from tubular elements shows apparent effect of geometry (restraint) on both low temperature volume expansion and the temperature at which accelerated … more
Date: May 5, 1964
Creator: Last, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Increased coolant flow H Reactor: PITA IP-27-I, Part 1. Supplement A

Description: Purpose of this supplement is to increase the maximum allowable liquid level in the near downcomer for single downcomer operation. The required clearance between the downcomer lid and liquid level is reduced from 24 inches to 18 inches in the near downcomer, providing bulk outlet temperature is maintained less than 93 C.
Date: February 5, 1964
Creator: Spicka, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Information report on downcomer instrumentation and data

Description: With recent concern for downcomer capacity at most areas, it seems appropriate that a survey be made to determine what instrumentation and data are available. The following is a brief description of the available instrumentation and data for KE, KW, H, F, DR, D, C, and B reactors.
Date: October 5, 1964
Creator: Zimmerman, P. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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