1,079 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Graphite Moderated Reactors"  
Results: 1 - 24 next
open access

Data Relating to Hanford Mined Graphite (2273-D) Samples Annealed at NAA

Description: On 2/8/1950, there was mined from process tube 2273 in D pile at Hanford a quantity of graphite power, which was expected to show the most extensive radiation damage of any graphite available at that time. A series of samples of this powder were annealed in 100 degrees increments from 100 degrees to 2000 degrees C at this labaoratory. There were returned to Hanford and shipped by them to the National Bureau of Standards for total stored energy measurements. The present memorandum is comprised o… more
Date: March 15, 1951
Creator: Smith, C. A. & Carter, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Graphite Isotope Ratio Method Development Report: Irradiation Test Demonstration of Uranium as a Low Fluence Indicator

Description: This report describes an irradiation test designed to investigate the suitability of uranium as a graphite isotope ratio method (GIRM) low fluence indicator. GIRM is a demonstrated concept that gives a graphite-moderated reactor's lifetime production based on measuring changes in the isotopic ratio of elements known to exist in trace quantities within reactor-grade graphite. Appendix I of this report provides a tutorial on the GIRM concept.
Date: October 20, 1999
Creator: Reid, B. D.; Gerlach, D. C.; Love, E. F.; McNeece, J. P.; Livingston, J. V.; Greenwood, L. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

US graphite reactor D&D experience

Description: This report describes the results of the U.S. Graphite Reactor Experience Task for the Decommissioning Strategy Plan for the Leningrad Nuclear Power Plant (NPP) Unit 1 Study. The work described in this report was performed by the Pacific Northwest National Laboratory (PNNL) for the Department of Energy (DOE).
Date: February 1, 1997
Creator: Garrett, S. M. K. & Williams, N. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of ASME Section III Task Group on Graphite Support Core Structures

Description: This report outlines the roadmap that the ASME Project Team on Graphite Core Supports is pursuing to establish design codes for unirradiated and irradiated graphite core components during its first year of operation. It discusses the deficiencies in the proposed Section III, Division 2, Subsection CE graphite design code and the different approaches the Project Team has taken to address those deficiencies.
Date: August 1, 2005
Creator: Bratton, Robert L. & Burchell, Tim D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Metal burning in graphite-moderated reactors

Description: Pinto beans, sweet corn, and zucchini squash (Cucurbita pepo var. black beauty) were grown in a randomized complete-block field/pot experiment at a site that contained the highest observed levels of surface gross gamma radioactivity within Los Alamos Canyon (LAC) at Los Alamos National Laboratory. Soils as well as washed edible and nonedible crop tissues were analyzed for various radionuclides and heavy metals. Most radionuclides, with the exception of {sup 3}H and {sup tot}U, in soil from LAC … more
Date: May 1, 1997
Creator: Wichner, R. P.; Ball, S. J.; Daw, C. S. & Thomas, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

RBMK thermohydraulic safety assessments using RELAP5/MOD3 codes

Description: The capability of the RELAP5/MOD3 code to validate various transients encountered in RBMK reactor postulated accidents has been assessed. The assessment results include a loss of coolant accident at the inlet of the core pressure tube, the blockage of a pressure tube, and the pressure response of the core cavity to in core pressure tube ruptures. These assessments show that the RELAP5/MOD3 code can predict major phenomena during postulated accidents in the RBMK reactors.
Date: June 1, 1995
Creator: Tsiklauri, G.V. & Schmitt, B.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Feasibility of Isotopic Measurements: Graphite Isotopic Ratio Method

Description: This report addresses the feasibility of the laboratory measurements of isotopic ratios for selected trace constituents in irradiated nuclear-grade graphite, based on the results of a proof-of-principal experiment completed at Pacific Northwest National Laboratory (PNNL) in 1994. The estimation of graphite fluence through measurement of isotopic ratio changes in the impurity elements in the nuclear-grade graphite is referred to as the Graphite Isotope Ratio Method (GIRM). Combined with reactor … more
Date: April 30, 2001
Creator: Wood, Thomas W.; Gerlach, David C.; Reid, Bruce D. & Morgan, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Report of the special study group

Description: The special study group was activated by a charter letter from Sub-Section Managers of Pile Technology on June 20, 1956. The principal objectives were: to collect the information which is presently available for new reactor design and to determine what information should be developed; to make a guess at pile variables; and to point out development programs which must be pursued to achieve a detailed design start in two years. The study was restricted to graphite moderated reactors with H{sub 2}… more
Date: July 18, 1956
Creator: Brown, J.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Installation of reactor gas refrigeration system -- 105-C, Project C-431

Description: It is recommended that the Design Committee approve the installation of a refrigeration system in the 105-C gas circulation system for removal of moisture from the reactor following a process tube leak as was previously approved by the C-431 Project Committed. Engineering studies show that this refrigeration system is necessary to provide sufficient water removal capacity in order that the water absorbing capacity of the system furnished by the silica gel towers will not be a limit to the rate … more
Date: March 5, 1953
Creator: Wells, H. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The physics design of accelerator-driven transmutation systems

Description: Nuclear systems under study in the Los Alamos Accelerator-Driven Transmutation Technology program (ADTT) will allow the destruction of nuclear spent fuel and weapons-return plutonium, as well as the production of nuclear energy from the thorium cycle, without a long-lived radioactive waste stream. The subcritical systems proposed represent a radical departure from traditional nuclear concepts (reactors), yet the actual implementation of ADTT systems is based on modest extrapolations of existing… more
Date: February 1, 1995
Creator: Venneri, F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Medium-size high-temperature gas-cooled reactor

Description: This report summarizes high-temperature gas-cooled reactor (HTGR) experience for the 40-MW(e) Peach Bottom Nuclear Generating Station of Philadelphia Electric Company and the 330-MW(e) Fort St. Vrain Nuclear Generating Station of the Public Service Company of Colorado. Both reactors are graphite moderated and helium cooled, operating at approx. 760/sup 0/C (1400/sup 0/F) and using the uranium/thorium fuel cycle. The plants have demonstrated the inherent safety characteristics, the low activatio… more
Date: August 1, 1980
Creator: Peinado, C.O. & Koutz, S.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Critical experiments in support of the CNPS (Compact Nuclear Power Source) program

Description: Zero-power static and kinetic measurements have been made on a mock-up of the Compact Nuclear Power Source (CNPS), a graphite moderated, graphite reflected, U(19.9% /sup 235/U) fueled reactor design. Critical configurations were tracked from a first clean configuration (184 most central fuel channels filled and all control rod and heat pipe channels empty) to a fully loaded configuration (all 492 fuel channels filled, core-length stainless steel pipe in the twelve heat-pipe channels, and approx… more
Date: January 1, 1988
Creator: Hansen, G. E.; Audas, J. H.; Martin, E. R.; Pederson, R. A.; Spriggs, G. D. & White, R. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The Graphite Isotope Ratio Method (GIRM): A Plutonium Production Verification Tool

Description: Over the lifetime of a production reactor, neutrons from the fission process not only convert U-238 into plutonium but also bring about changes in the elements of the reactor's core components. Components such as shielding, pressure vessels, coolant piping, control rods, structural supports, and, in the case of graphite moderated reactors, the solid graphite moderator are all affected. Because a reactor's total plutonium production is directly related to total neutron fluence, and, likewise, ch… more
Date: January 1, 1999
Creator: McNeece, JP; Reid, BD & Wood, TW
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The first reactor [40th anniversary commemorative edition]

Description: This updated and revised story of the first reactor, or 'pile,' commemorates the 40th anniversary of the first controlled, self-sustaining nuclear chain reaction created by mankind. Enrico Fermi and his team of scientists initiated the reaction on December 2, 1941, underneath the West Stands of Stagg Field at the University of Chicago. Firsthand accounts of the participants as well as postwar recollections by Enrico and Laura Fermi are included.
Date: December 1, 1982
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of EPRI nuclear power division research topics supportive of HTGR technology

Description: For HTGR commercialization studies, an LWR/HTGR Technology Transfer program was devised. Candidate programs were identified out of a total of 208 EPRI NPD (Nuclear Power Division) projects. Of these, 26 project areas presented the highest probability for technology transfer. (DLC)
Date: October 6, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gas-cooled reactors

Description: Experience to date with operation of high-temperature gas-cooled reactors has been quite favorable. Despite problems in completion of construction and startup, three high-temperature gas-cooled reactor (HTGR) units have operated well. The Windscale Advanced Gas-Cooled Reactor (AGR) in the United Kingdom has had an excellent operating history, and initial operation of commercial AGRs shows them to be satisfactory. The latter reactors provide direct experience in scale-up from the Windscale exper… more
Date: January 1, 1976
Creator: Schulten, R. & Trauger, D. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Consolidated Fuel Reprocessing Program. Progress report, January 1 to March 31, 1979

Description: On Oct. 1, 1978, a transition phase was begun to concentrate all US fuel reprocessing research in one major program, the Consolidated Fuel Reprocessing Program (CFRP). The CFRP is organized into the following: process R and D, engineering research, engineering systems, technical support, HTGR fuel reprocessing, and pyrochemical and dry processing methods. Progress is reported in each area. (DLC)
Date: June 1, 1979
Creator: Unger, W.E. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CHAP: a composite nuclear plant simulation program applied to the 3000 MW(t) HTGR

Description: The Composite HTGR Analysis Program (CHAP) is a general systems analysis program which has been developed at LASL. The program is being used for simulating large HTGR nuclear power plant operation and accident transients. The general features and analytical methods of the CHAP program are discussed. Features of the large HTGR model and results of model transients are also presented.
Date: January 1, 1977
Creator: Secker, P. A.; Bailey, P. G.; Gilbert, J. S.; Willcutt, G. J. E. Jr. & Vigil, J. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Assessment of very high-temperature reactors in process applications

Description: An overview is presented of the technical and economic feasibility for the development of a very high-temperature reactor (VHTR) and associated processes. A critical evaluation of VHTR technology for process temperatures of 1400 and 2000/sup 0/F is made. Additionally, an assessment of potential market impact is made to determine the commercial viability of the reactor system. It is concluded that VHTR process heat in the range of 1400 to 1500/sup 0/F is attainable with near-term technology. How… more
Date: November 1, 1976
Creator: Spiewak, I.; Jones, J. E. Jr.; Gambill, W. R. & Fox, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Graphite Isotope Ratio Method: A Primer on Estimating Plutonium Production in Graphite Moderated Reactors

Description: The Graphite Isotope Ratio Method (GIRM) is a technique used to estimate the total plutonium production in a graphite-moderated reactor. The cumulative plutonium production in that reactor can be accurately determined by measuring neutron irradiation induced isotopic ratio changes in certain impurity elements within the graphite moderator. The method does not require detailed knowledge of a reactor's operating history, although that knowledge can decrease the uncertainty of the production estim… more
Date: March 25, 2004
Creator: Gesh, Christopher J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

350 MW(t) MHTGR preassembly and modularization

Description: The Modular High Temperature Gas Cooled Reactor (MHTGR) provides a safe and economical nuclear power option for the world's electrical generation needs by the turn of the century. The proposed MHTGR plant is composed of four 350 MW(t) prismatic core reactor modules, coupled to a 2(2 {times} 1) turbine generator producing a net plant electrical output of 538 MW(e). Each of the four reactor module is located in a below-ground level concrete silo, and consists of a reactor vessel and a steam gener… more
Date: May 1, 1991
Creator: Venkatesh, M.C. (General Atomics, San Diego, CA (USA)); Jones, G. (Gas-Cooled Reactor Associates, San Diego, CA (USA)); Dilling, D.A. (Bechtel International Corp., San Francisco, CA (USA)) & Parker, W.J. (Stone and Webster Engineering Corp., Boston, MA (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

HTGR spent fuel storage study

Description: This report documents a study of alternate methods of storing high-temperature gas-cooled reactor (HTGR) spent fuel. General requirements and design considerations are defined for a storage facility integral to a fuel recycle plant. Requirements for stand-alone storage are briefly considered. Three alternate water-cooled storage conceptual designs (plug well, portable well, and monolith) are considered and compared to a previous air-cooled design. A concept using portable storage wells in racks… more
Date: April 1, 1979
Creator: Burgoyne, R. M. & Holder, N. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen