UNT Libraries Government Documents Department - 55 Matching Results

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710 Reactor thermoelectric space power system concepts

Description: Declassified 21 Sep 1973. A preliminary evaluation of the use of the 710 Reactor in an auxiliary space power system utilizing thermoelectric converters has been performed in order to determine feasibility of the concept and to define the required 710 fuel system operating conditions. Included are results of thermodynamic cycle studies and characteristics of the major components for a range of power levels. Configuration arrangements for man rated and instrument rated 50 kw(e) systems are shown.… more
Date: September 1, 1967
Creator: Flitner, D.P.
Item Type: Refine your search to only Report
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Aerospace nuclear safety report for August 1967

Description: The AEC Safety Branch advised that the present outlook for a potential mission using four modified SNAP-3 type generators is rather negative. Drop tests of four SNAP-19 intact reentry heat source capsules were conducted at the Tonopah Test Range. A preliminary GE SNAP-27 safety analysis was reviewed. Three arc tunnel tests were conducted at low heat fluxes. Debris were collected on downrange impactors from all tests. The rapid helium depressurization test on fuel microspheres was conducted by B… more
Date: September 1, 1967
Creator: Illing, R.G. (comp.)
Item Type: Refine your search to only Report
open access

Behavior of Fission Products Released Into a Steam-Air Atmosphere From Overheated UO {Sub 2} Previously Irradiated to 20,000 MWD/T (Nuclear Safety Pilot Plant Run No. 14, Part I)

Description: This report summarizes the results of the first run made in the Nuclear Safety Pilot Plant using Zircaloy-2 clad UO2 irradiated to 20,000 MWD/T and reirradiated shortly before the run to replenish the inventory of short-lived fission products.
Date: September 27, 1967
Creator: Parsly, L. F. & Row, T. H.
Item Type: Refine your search to only Report
open access

Determination of uniaxial mechanical properties of unirradiated and irradiated Hastelloy-N bar and biaxial stress-rupture properties of chromized and coated unirradiated Hastelloy-N

Description: Short-time tensile tests were conducted on irradiated (2 x 10/sup 20/ nvt) and unirradiated Hastelloy-N bar from heats 5911 and 6252. No significant difference in mechanical properties was noted between the two heats. The 1200/sup 0/F ultimate tensile strength was decreased by irradiation from 65 to 80 ksi and 48 to 52 ksi. The 1400/sup 0/F ultimate tensile strength was decreased from 45 to 51 ksi to 32 to 34 ksi. The yield strength was not greatly affected by irradiation at either 1200 or 1400… more
Date: September 8, 1967
Creator: Stearns, J.D.
Item Type: Refine your search to only Report
open access

Development Report Number 6: Saline Water Conversion Demonstration Plant Number 1, Freeport, Texas

Description: Report regarding the eighth Development Run of Saline Water Conversion Demonstration Plant Number 1. Primary objectives include studying "various aspects of heat transfer and water treatment and their effect on the Multiple-Effect Long-Tube-Vertical Evaporation Process" (p. 1).
Date: September 1967
Creator: Stearns-Roger Corporation
Item Type: Refine your search to only Report
open access

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
open access

Experimental Search for a Heavy Electron.

Description: A search for a heavy electron of the type considered by Low and Blackmon has been made by studying the inelastic scattering of 5 BeV electrons from hydrogen. The search was made over a range of values of the mass of the heavy electron from 100 to 1300 MeV. No evidence for such a particle was observed. Upper limits on the production cross sections were determined and employed to deduce limits on the values of the electron-photon-heavy electron coupling constant in Low and Blackmon's theory.
Date: September 1, 1967
Creator: Boley, C.D.; Elias, J.E.; Friedman, J.I.; Hartmann, G.C.; Kendall, H.W.; Kirk, P.N. et al.
Item Type: Refine your search to only Report
open access

The first weighing of plutonium

Description: The following text, transcribed from the remarks of those scientists who gathered at the University of Chicago on September 10, 1967, to celebrate the 25th anniversary of the first weighing of plutonium, tells an important part of the story of this fascinating new element that is destined to play an increasingly significant role in the future of man.
Date: September 10, 1967
Item Type: Refine your search to only Article
open access

HRT PROCESS FLOWSHEETS (REVISION IV)

Description: The first four process flowsheets were drawn to show the division between the high and low pressure fuel and blanket systems. This necessitated the repetition of certain equipment which fell at the dividing points, such as the letdown heat exchangers, the feed pumps, etc. They were also designed to make it possible to cut the sheets and join them to make one large flowsheet without repetition of equipment or lines. In general the flowsheet line numbers on the fuel side are a 100 series and the … more
Date: September 16, 1967
Creator: Zapp, F C
Item Type: Refine your search to only Report
open access

Hupmobile cloud chamber parameters

Description: The accompanying table lists the presently selected parameters for the twelve cloud chambers. The chambers are numbered consecutively from 4 through 15 as they are lined up in the bunker. The lowest number is closest to the source. All except the first chamber have some thin metal filters to attenuate the flux and harden the spectrum. Cloud chambers 10, 12, and 14 are shielded by a collimator with about 200 pinholes in it. The flux in these chambers is attenuated by the ratio of the pinhole are… more
Date: September 28, 1967
Creator: Hansen, N. E.
Item Type: Refine your search to only Report
open access

A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments

Description: Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and … more
Date: September 1967
Creator: Bryant, Lawrence T.; Amiot, Lawrence W.; Dickerman, Charles E. & Stephany, William P.
Item Type: Refine your search to only Report
open access

Long range plan - Plowshare excavation program (Book 1 - 1966/1967 excavation program binder)

Description: The purpose of this report is to present a proposed five-year program for the Plowshare Excavation Program. In preparing this study we proceed as follows: (a) Review the significant advances (since 1963) in nuclear excavation technology, and (b) identify the key uncertainties in that technology. After completing these two steps, we then proceed to identify key experiments and any new measurements that may be required to increase our predictive capability and/or to resolve the major uncertaintie… more
Date: September 7, 1967
Creator: Knox, J. B.
Item Type: Refine your search to only Report
open access

Low-cycle fatigue testing of irradiated Hastelloy-N (ORR S-2)

Description: Hastelloy-N strip specimens were irradiated in the Oak Ridge Research Reactor at temperatures of 1330 to 1390/sup 0/F, to neutron doses of 1.8 to 2.6 x 10/sup 20/ nvt thermal, l.4 to 2.0 x 10/sup 19/ nvt fast. Twelve irradiated specimens were selected for testing from each of two heats, 0143 (0.010 in. thick) and 5911 (0.015 in.). Six specimens in each heat were as-received, the other six were as-processed. Processing steps included chromizing, a simulated coating firing cycle, diffusion treatm… more
Date: September 28, 1967
Creator: Krupp, W. E. & Johnson, L. L.
Item Type: Refine your search to only Report
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