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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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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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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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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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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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Hanford Engineer Works technical progress letter No. 134, January 19--25, [1947]

Description: This technical progress letter contains reports from six Technical Department divisions at the Hanford Engineer Works for January 19 through January 25, 1947. The six reporting divisions are: 100 Areas, 300 Area, 200 Areas, Chemical Development, Laboratories, and Statistical Studies. (JL)
Date: January 30, 1947
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Investigation of KW reactor incident

Description: The new KW reactor was placed in operation on January 4, 1955, and had been running at relatively low power levels for only 17 hours when it was shut down because of a process tube water leak which appeared to be associated with a slug rupture. After several days of unrewarding effort to remove the slugs and tube by customary methods, it developed that considerable melting of the tube and slugs had taken place. It was then evident that removal of the stuck mass and repairs to the damaged tube c… more
Date: February 11, 1955
Creator: Sturges, D. G.; Hauff, T. W. & Greager, O. H.
Partner: UNT Libraries Government Documents Department
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TRAC-PF1/MOD3 calculations of Savannah River Laboratory Rig FA single-annulus heated experiments

Description: This paper presents the results of TRAC-PF1/MOD3 benchmarks of the Rig FA experiments performed at the Savannah River Laboratory to simulate prototypic reactor fuel assembly behavior over a range of fluid conditions typical of the emergency cooling system (ECS) phase of a loss-of-coolant accident (LOCA). The primary purpose of this work was to use the SRL Rig FA tests to qualify the TRAC-PF1/MOD3 computer code and models for computing Mark-22 fuel assembly LOCA/ECS power limits. This qualificat… more
Date: March 1, 1992
Creator: Fischer, S. R. & McDaniel, C. K.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: February 1961

Description: This is the monthly report for the Hanford Laboratories Operation, February 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: March 15, 1961
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Risk management activities at the DOE Class A reactor facilities

Description: The probabilistic risk assessment (PRA) and risk management group of the Association for Excellence in Reactor Operation (AERO) develops risk management initiatives and standards to improve operation and increase safety of the DOE Class A reactor facilities. Principal risk management applications that have been implemented at each facility are reviewed. The status of a program to develop guidelines for risk management programs at reactor facilities is presented.
Date: December 31, 1993
Creator: Sharp, D. A.; Hill, D. J.; Linn, M. A.; Atkinson, S. A. & Hu, J. P.
Partner: UNT Libraries Government Documents Department
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The storage and handling of J-slugs

Description: The nuclear safety specifications (1) for handling J-slugs have previously been reviewed. These specifications provided information for the storage of loaded 100-hole shipping containers and loaded 66-hole wood cart pallets in certain arrays. Storage of J-slugs in J-Material Crates conforming to Drawing No. H-3-6217 had not been reviewed for the previous specifications. It has become desirable to provide specifications for J-slug storage in these crates as well as make additions to the present … more
Date: February 7, 1956
Creator: Ketzlach, N.
Partner: UNT Libraries Government Documents Department
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