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Gas cooling of cylindrical control rods for pile Area ``G``: Preliminary report

Description: A first approximation of the gas required to cool control rods for Pile Area G is presented in the following report. Since the results are based on a number of assumptions and approximations, they should be considered only as a first approximation and subject to revision. A gadolinium-stainless steel control rod can probably be readily cooled by gas. A boron-stainless steel control rod would be difficult to cool with gas and would probably require about 1,000 lbs./hr. of helium per rod. Carbon … more
Date: March 23, 1950
Creator: Robbins, C. H.
Partner: UNT Libraries Government Documents Department
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Review of effluent disposal practices in N Reactor Department

Description: A survey has been conducted of current methods of disposal of radioactive, chemical, and sanitary wastes used both at the 100 Area and 300 Area sites of N Reactor Department Operations. In addition, liquid storage facilities have been surveyed for situations which might result in river water pollution. The survey and this report have been prepared in response to the request of the Manager, Richland Operations Office of the Atomic Energy Commission in accordance with Executive Order 11258. An au… more
Date: February 28, 1966
Creator: Stepnewski, D. D. & Hendrickson, M. M.
Partner: UNT Libraries Government Documents Department
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An exploratory analysis of thermal-hydraulic conditions leading to severe accidents for the New Production Heavy-Water Reactor

Description: This study, sponsored by the New Production Reactor (NPR) Program through the Los Alamos NPR Safety Project Office, is part of the body of severe-accident review information being developed to support the safety review of the New Production Heavy-Water Reactor (NP-HWR). The NP-HWR safety study of severe beyond-design-basis events concerns two issues related to in-vessel, sudden-energy sources: wet-core recriticality and molten-fuel-and-coolant interaction (MFCI). The configuration that will lea… more
Date: December 1, 1992
Creator: Cheng, Teh-Chin
Partner: UNT Libraries Government Documents Department
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Validation and verification of RELAP5 for Advanced Neutron Source accident analysis: Part I, comparisons to ANSDM and PRSDYN codes

Description: As part of verification and validation, the Advanced Neutron Source reactor RELAP5 system model was benchmarked by the Advanced Neutron Source dynamic model (ANSDM) and PRSDYN models. RELAP5 is a one-dimensional, two-phase transient code, developed by the Idaho National Engineering Laboratory for reactor safety analysis. Both the ANSDM and PRSDYN models use a simplified single-phase equation set to predict transient thermal-hydraulic performance. Brief descriptions of each of the codes, models,… more
Date: December 1, 1993
Creator: Chen, N. C. J.; Ibn-Khayat, M.; March-Leuba, J. A. & Wendel, M. W.
Partner: UNT Libraries Government Documents Department
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Vernatherm functional test, Test Project No. 14

Description: The Vernatherm unit is a temperature sensitive capsule which translates temperature change to mechanical movement of a brass plunger. A change in phase of a hydrocarbon contained in a cylinder caused by temperature change, causes movement of the brass plunger. The units are available for various temperature ranges. The adaptation considered was to monitor the outlet water temperature from individual process tubes in the ``G`` pile. The purpose of the test was to determine the magnitude of error… more
Date: October 31, 1951
Creator: Smith, J. L.
Partner: UNT Libraries Government Documents Department
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Best-estimate Mark 22 power and temperature limits during the flow instability phase of K Reactor LBLOCAs

Description: Los Alamos National Laboratory (LANL) has been providing independent analyses to the Department of Energy in its endeavor to enhance the safe operation of the K Reactor located at the Savannah River Laboratory (SRL). LANL has performed neutronic and thermal-hydraulic system simulations to assess the impact of hypothesized accidents in the K Reactor. In particular, the large-break loss-of-coolant accident (LBLOCA) was one of the major transients that was analyzed. The LBLOCA consists of two dist… more
Date: March 1, 1992
Creator: Rodriguez, S.; Steiner, J.; Motley, F. & Morgan, M.
Partner: UNT Libraries Government Documents Department
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C-Reactor I and E loading instability limits

Description: The pilot charging of I & E fuel elements has been implemented at C-Reactor under Production Test IP-19-A. It was necessary to provide adequate tube protection against flow interruption by establishing proper trip setting on the Panellit pressure gauges. the administration of these Panellit trip settings is done by trip-before- boiling tube outlet temperature limits, which are similar in principle to the current instability limits. Trip-before-boiling limits for C-Reactor I & E fuel elements lo… more
Date: January 24, 1957
Creator: Hess, K. W.
Partner: UNT Libraries Government Documents Department
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Final report on Production Test 105-528-A -- Alteration of two C-Pile horizontal safety rods for temperature distribution control

Description: Pile temperature control is normally maintained by using four horizontal rods, two ``long`` rods extending to the far side of the pile and two ``short`` rods whose tips are on the near side. (1) This procedure prevents cycling of ``hot spots`` about the pile, but does not achieve symmetrical horizontal temperature distribution. Prior to pile operation the cadmium-containing cans were removed from the near ends of the two ``long`` control rods, numbers 5 and 11, at C pile, so that when these rod… more
Date: June 11, 1953
Creator: Halliday, A. W.
Partner: UNT Libraries Government Documents Department
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Status report of confinement studies Douglas United Nuclear operated reactors

Description: Confinement studies on the Hanford Production reactors were started in March at the request of the Richland Operations Office. The confinement studies were then undertaken with the following objectives established: (1) review and reestablish if necessary, the maximum credible accident for the production reactors operated by Douglas United Nuclear (DUN); (2) evaluate the present confinement systems under the Code of Federal Regulation Title 10, Part 100, Reactor Site Criteria, for the maximum cr… more
Date: November 30, 1965
Creator: Spink, J. R. & Fifer, N. F.
Partner: UNT Libraries Government Documents Department
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Radioisotope concentrations in the PRTR primary coolant and helium system during operation with a failed fuel element(s)

Description: Fission product measurements in the PRTR primary D{sub 2}O and helium systems during the startup tests in May 1961, showed the presence of a defective fuel elements(s). Reactor operation was discontinued during the latter part of May and during June for reactor maintenance and fuel element inspection. On resumption of operation on July 1, a sampling and analytical program was initiated to study the radioisotope concentrations resulting from this defective element(s) which were present in the pr… more
Date: September 7, 1961
Creator: Perkins, R. W. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: January 1961

Description: This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: February 15, 1961
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Reactor Safety Analysis Computer Program Features That Enhance User Productivity

Description: This paper describes several design features of the MARY computer program that increase user productivity. The MARY program was used to analyze behavior of the Savannah River Site (SRS) K Reactor during postulated nuclear and thermal-hydraulic transients, such as overpower and underflow events, before K Reactor was placed in cold standby in 1993. These analyses provide the bases for portions of the accident chapter of the K-Reactor Safety Analysis Report.
Date: 1993-23~
Creator: Burnett, T. W. T.; Cleaver, B. H.; Fields, C. C.; McKinney, J. S.; Wooten, L. A. & Finfrock, S. H.
Partner: UNT Libraries Government Documents Department
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Intelligent distributed control for nuclear power plants. Third annual technical progress report, September 1991--October 1992

Description: This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Third Annual Technical Progress report summarizes the period from September 1991 to October 1992. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. His philosophy, is to improve public percep… more
Date: September 30, 1992
Creator: Klevans, E. H.
Partner: UNT Libraries Government Documents Department
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Report on decreasing available acceleration of 190-B process pump turbines in order to reduce emergency steam demand

Description: As originally installed, the primary process pump turbines in 190-B were arranged to accelerate considerably upon loss of BPA electric power supply to the Process Pump House. However, the acceleration comes too late to be of value in maintaining top of riser pressure within the first second or two, and the acceleration results only in maintaining final process water pressure and flow at values higher than needed. It is desired to limit the acceleration of the turbines to a relatively small amou… more
Date: December 28, 1951
Partner: UNT Libraries Government Documents Department
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Oral histories at the Hanford Nuclear Reservation

Description: The founding of the Hanford Engineering Works to produce plutonium is described. The 45-year defense mission has now been replaced with a peaceful mission, that of being the first site for massive cleanup of the 45-year nuclear waste. In order to establish a remedial investigation and feasibility plan, a process of discovery named the Technical Baseline Report must be performed; the task of this process is to discover all that is known about a proposed cleanup site (what the waste was, where di… more
Date: March 1, 1992
Creator: DeFord, D. H.
Partner: UNT Libraries Government Documents Department
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SP-100 fuel pin performance: Results from irradiation testing

Description: A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pin are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-re… more
Date: September 1, 1993
Creator: Makenas, B. J.; Paxton, D. M.; Vaidyanathan, S. & Hoth, C. W.
Partner: UNT Libraries Government Documents Department
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Final report on Production Test 105-58-P -- B Pile reactivity under shutdown conditions

Description: Following the shutdown of the B Pile in March 1946 a method was devised for monitoring the sub-critical reactivity such that any significant change in neutron flux would be detected. This report summarizes the status of the unit until its start up in July 1948.
Date: July 19, 1948
Creator: Kruesi, F. E.
Partner: UNT Libraries Government Documents Department
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Final report on Production Test No. 105-1-MR -- Poison column control during reactor operation

Description: The lack of control rod capacity in the reactors with nine rods is causing significant production losses. The present control system, which functioned satisfactorily at a 300 MW equilibrium power level, is unable to counteract the larger startup reactivity transient effects at the current high power levels. This lack of strength causes the power level to be restricted during startup. The control system is also not flexible enough to prevent outages for the discharge of temporary poison. (1) A m… more
Date: July 24, 1952
Creator: Schilling, R. D. & Hess, K. W.
Partner: UNT Libraries Government Documents Department
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Stewards of a national resource

Description: Events of the past several years have had a profound impact on the mission of the Department of Energy. Most notably, the end of the Cold War has made it possible for us to reorient our mission from primarily the design, production, and testing of nuclear weapons toward: increasing efficiency and the choice of energy sources, supporting basic and applied research in science and technology, addressing environmental quality issues, improving industrial competitiveness, and a continued contributio… more
Date: January 1, 1995
Partner: UNT Libraries Government Documents Department
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In-reactor performance of LWR-type tritium targe rods

Description: Pacific Northwest Laboratory (PNL) has conducted several one-year irradiation tests of light-water reactor (LWR)-type tritium target rods. This report discusses these tests which have been sponsored by DOE`s Office of New Production Reactors. The first test, designated water capsule-I (WC-1), was conducted in the Advanced Test Reactor (ATR) at DOE`s Idaho National Engineering Laboratory from November 1989 to December 1990. The test vehicle contained a single four-foot target rod within a pressu… more
Date: June 1, 1992
Creator: Lanning, D. D.; Paxton, M. M. & Crumbaugh, L.
Partner: UNT Libraries Government Documents Department
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