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Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, January 1, 1979-March 31, 1979

Description: This report presents the results of work performed from January 1, 1979 through March 31, 1979 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high tempera… more
Date: July 19, 1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electron Microscopy of Fission Fragment Damage in Aluminum-Uranium Fuel Element

Description: Technical report covering an extensive investigation of the nature of fission fragment "damage" in various metals. During the investigation electron micrographs of fission fragment tracks in the BNL Graphite Reactor fuel element cores were made.
Date: June 19, 1962
Creator: Kelsch, J. J. & Kammerer, O. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Damage in Graphite. [Part] 1, The Activation Energy for Annealing Single Interstitials in Neutron Irradiated Graphite and the Absolute Rate of Formation of Displaced Atoms

Description: Technical report that attempts to address the controversy regarding the activation energy for the process of annealing single interstitials in irradiated graphite. The experiments determined that "the activation energy for the process of annealing single interstitials in neutron irradiated graphite and the absolute rate of formation of displaced atoms have been determined..." from the abstract.
Date: June 19, 1962
Creator: Schweitzer, Donald G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of Hanford production capability through fiscal year 1973

Description: A letter dated June 3, 1963 to W, E. Johnson, General Manager, Hanford Atomic Products Operation, from J. E. Travis, Manager, Richland Operations Office requested an updated study on the expected life of existing production reactors similar to Sections II, III and IV of document HW-59000. This study covers the ten year period to FY 1973 as the previous study document covered the ten year period FY 1958 to Fy 1968. In Section II, production has been forecast for the existing plant with no improv… more
Date: June 19, 1963
Creator: Greninger, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of reactor graphite distortion problems

Description: The purpose of this document is primarily to discuss the effects of current retubing programs on the graphite moderator of the K Reactors. A secondary purpose of this report is to present general information related to graphite arrangement and keying patterns at the other operating reactors and to review, in a limited way, the types of graphite distortion observed at these reactors.
Date: November 19, 1962
Creator: Coughren, K. D.; Kempf, F. J. & Munro, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Graphite expansion committee meeting of January 7, 1947

Description: The fourteenth meeting of the Graphite Expansion Committee was held on February 7, 1947. Laboratory studies indicate that either the graphite thermocouples are reading low or that annealing effects at elevated temperatures within the pile are much greater than those encountered In the laboratory. Current difficulties with operation of some of the horizontal and vertical control rods seem to be attributable to graphite expansion, though no complete understanding of the phenomena has been obtaine… more
Date: February 19, 1947
Creator: Woods, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal shield cooling tube surveillance: B, C, D, and K Reactors

Description: The top thermal shields of the Hanford reactors were formed by placing single layers of large cast iron blocks on the top of the graphite stacks. Accumulative distortion of the graphite stack is causing several inches of variation in the elevation of the originally level top thermal shields. The integrity of the top thermal shield cooling tubes is of concern because of the high axial and bending stresses they are subjected to from the shield variations in addition to the normal service conditio… more
Date: November 19, 1964
Creator: Bonham, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Water treatment program - old reactors

Description: Conclusions resulting from a recent corrosion study, together with evidence of graphite damage possibly occurring during retubing operations (having obvious implications in regard to reactor life), initiated a critical assessment of the water treatment process. This study was undertaken to determine whether immediate or near-term process changes could be made at the older reactors to minimize aluminum corrosion without causing adverse effects in other areas.
Date: November 19, 1962
Creator: Geier, R. G. & Van Wormer, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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M-1 N-Reactor fuel development. Excerpts from N-Reactor Department Research and Development Budget for FY-1967 and Revision of Budget for FY-1966

Description: The use of metallic uranium fuel elements on a large scale in a pressurized water cooled graphite moderated power reactor environment in N-Reactor not only represents an extrapolation from previous Hanford fuel technology but it represents the only production-scale application of this concept in this country or abroad. Provision of a supporting technology is and will continue to be a major activity at Hanford as only a limited amount of directly applicable R&D will be available from other sites… more
Date: April 19, 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PT-IP-759, channel caulking tests: C Reactor

Description: The graphite movement which has occurred at the various reactors has been characterized by two problems: (1) Crooked channels and (2) cracks and miscellaneous voids where pieces of blocks are missing. Of these problems, the cracks and voids have been the most serious in the case of ball drops. Alleviation of the crooked channels can sometimes be accomplished by graphite removal methods such as broaching, but unless some method is found to prevent the balls from entering cracks, the total effect… more
Date: March 19, 1965
Creator: Cooke, J. P. & Russell, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production Test IP-725, Supplement A: Increased graphite temperature limit F Reactor

Description: The objective of Production Test IP-725 was to investigate the reaction rate between graphite and carbon dioxide in F Reactor at a temperature 50 C higher than that currently permitted by Process Standards. After approval of the test, the temperature limit was increased from 650 to 700 C. After approximately three weeks of operation with the-higher temperature limit, the reactor was shut down and the graphite oxidation monitor samples which had been inserted for this test were discharged and me… more
Date: March 19, 1965
Creator: Russell, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100 Areas technical activities report -- Engineering, June, 1948

Description: This report covers work done by the Pile Engineering Groups and work done on special assignments. Topics covered include: slug blistering and corrosion; graphite allocation to DR pile; slug molding; segmental discharge; Van Stone corrosion; flow laboratory modifications; downcomer at B pile; downcomer at D pile; annealing of pile graphite; replacement of pile atmosphere with CO{sub 2}; unit motion; beta experiment; can opening; slug annealing; new technical building, 300 area; and ruptured slug… more
Date: July 19, 1948
Creator: Woods, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Depressurization accident analyses for the Fort St. Vrain Reactor

Description: Design-basis depressurization accident analyses for the Fort St. Vrain reactor were performed using the FLODIS (Ref. 4) code. The FLODIS code models the active core, side reflector, gas annulus between the core barrel and the PCRV liner, and the PCRV cooling system. Results are presented for the Pelton circulators operating at 10,550, 8800, and 7000 rpm. Maximum temperatures of selected components are plotted as a function of time during the transient. None of the components studied exceeded th… more
Date: November 19, 1976
Creator: Paul, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100 Areas: April 9--April 15

Description: Reported are: physics (B Pile, D Pile, F Pile, general physics); and water, corrosion, and engineering (process water control and pressure drop studies, purging studies, corrosion, graphite expansion, downcomer -- B Area).
Date: April 19, 1946
Creator: Jordan, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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K Water Plant improvements

Description: A Task Force was established in the Irradiation Processing Department to examine the K-Reactor Water Plant to (1) review the operating and maintenance experience with the water plant as improved since startup, (2) identify major plant additions which could further improve reliability, and (3) estimate the costs of any such additions. The K-Water Plant basically consists of the electrically driven primary cooling system with power supplied by the BPA system, electrically driven secondary or back… more
Date: March 19, 1959
Creator: Trumble, R. E.; Heacock, H. W.; Reinig, L. P.; Jones, S. S. & Mollerus, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mechanical Design of the NSTX Liquid Lithium Divertor

Description: The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium divertor in a high-power magnetic confinement device. It will replace part of the lower outboard divertor between a specified inside and outside radius, and ultimately provide a lithium surface exposed to the plasma with enough depth to absorb a significant particle flux. There are numerous technical challenges involved in the design. The lithium layer must be as thin as possible, and maintained … more
Date: February 19, 2009
Creator: R. Ellis, R. Kaita, H. Kugel, G. Paluzzi, M. Viola and R. Nygren
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Lithium Surface Coatings for Improved Plasma Performance in NSTX

Description: NSTX high-power divertor plasma experiments have shown, for the first time, significant and frequent benefits from lithium coatings applied to plasma facing components. Lithium pellet injection on NSTX introduced lithium pellets with masses 1 to 5 mg via He discharges. Lithium coatings have also been applied with an oven that directed a collimated stream of lithium vapor toward the graphite tiles of the lower center stack and divertor. Lithium depositions from a few mg to 1 g have been applied … more
Date: February 19, 2008
Creator: Kugel, H. W.; Ahn, J.-W.; Allain, J. P.; Bell, R.; Boedo, J.; Bush, C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Dual Channel X-ray Spectrometer for Fast Ignition Research

Description: A new Dual Channel Highly Ordered Pyrolytic Graphite (DC-HOPG) x-ray spectrometer was developed to study laser-generated electron beam transport. The instrument uses a pair of graphite crystals and has the advantage of simultaneously detecting self emission from low-Z materials in first diffraction order and high-Z materials in second order. The emissions from the target are detected using a pair of parallel imaging plates positioned in a such way that the noise from background is minimized and… more
Date: April 19, 2010
Creator: Akli, K. U.; Patel, P. K.; Van Maren, R.; Stephens, R. B.; Key, M. H.; Higginson, D. P. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Dispersions of Uranium Carbides in Aluminum Plate-Type Research Reactor Fuel Elements

Description: The technical feasibility of employing uranium carbide aluminun dispersions in aluminum-base research reactor fuel elements was investigated This study was motivated by the need to obtain higher uranium loadings in these fuel elements. Although toe MTR-type unit, containing a 13 18 wt% U-Al alloy is a proven reactor component, fabrication problems of considerable magnitude arise when attempts are made to increase the uranium investment in the alloy to more than 25 wt.%. Au approach to these fab… more
Date: November 19, 1959
Creator: Thurber, W. C. & Beaver, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CRITICALITY SAFETY CONTROL OF LEGACY FUEL FOUND AT 105-K WEST FUEL STORAGE BASIN

Description: In August 2004, two sealed canisters containing spent nuclear fuel were opened for processing at the Hanford Site's K West fuel storage basin. The fuel was to be processed through cleaning and sorting stations, repackaged into special baskets, placed into a cask, and removed from the basin for further processing and eventual dry storage. The canisters were expected to contain fuel from the old Hanford C Reactor, a graphite-moderated reactor fueled by very low-enriched uranium metal. The expecte… more
Date: August 19, 2005
Creator: Jensen, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Trace, isotopic analysis of micron-sized grains -- Mo, Zr analysis of stardust (SiC and graphite grains).

Description: Secondary Neutral Mass Spectrometry using resonant laser ionization can provide for both high useful yields and high discrimination while maintaining high lateral and depth resolutions. An example of the power of the method is measurement of the isotopic composition of Mo and Zr in 1-5 {micro}m presolar SiC and graphite grains isolated from the Murchison CM2 meteorite for the first time. These grains have survived the formation of the Solar System and isotopic analysis reveals a record of the s… more
Date: February 19, 1998
Creator: Pellin, M. J. & Nicolussi, G. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Instrumentation for the determination of material properties from spectroscopic measurements of total integrated scatter

Description: A variety of important optical properties can be determined from spectroscopic analysis of diffuse reflectance of surfaces. The design of a small user friendly, light-weight, field hardened, computer controlled device for performing infrared spectroscopic analysis of trace contaminants on surfaces is described. The device employs a miniature Fourier transform infrared (FTIR) spectrometer with very efficient diffuse reflectance optics and a portable computer to provide reflectance spectra of sur… more
Date: June 19, 1995
Creator: Powell, G. L.; Barber, T. E. & Neu, J. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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