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DYNAPCON: A Computer Code for Dynamic Analysis of Prestressed Concrete Structures

Description: A finite element computer code for the transient analysis of prestressed concrete reactor vessels (PCRVs) for LMFBR containment is described. The method assumes rotational symmetry of the structure. Time integration is by an explicit method. The quasistatic prestressing operation of the PCRV model is performed by a dynamic relaxation technique. The material model accounts for the crushing and tensile cracking in arbitrary direction in concrete and the elastic-plastic behavior of reinforcing ste… more
Date: September 1982
Creator: Marchertas, A. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of REXCO Code Predictions with SRI SM-2 Experimental Results

Description: This report deals with the REXCO-code predictions of the SRI SM-2 test. Two calculations were performed with the REXCO-HEP code: one used the pressure history of the core detonation products as input and the other the pressure-volume relations of the detonation products as input. The other inputs of the computer analysis are the vessel and the core-barrel dimensions and boundary conditions, the constitutive equations of the vessel and the core barrel materials, and the equation of state for the… more
Date: August 1978
Creator: Chang, Y. W. & Gvildys, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design-Development and Operation of the Experimental Boiling-Water Reactor (EBWR) Facility, 1955--1967

Description: The Experimental Boiling-Water Reactor (EBWR) was designed, built, and operated to provide experience and engineering data that would demonstrate the feasibility of the direct-cycle, boiling-water reactor and be applicable to improved, larger nuclear power stations; and was based on information obtained in the first test boiling-water reactors, the BORAX series. EBWR initially produced 20 MW(t), 5 MW(e); later modified and upgraded, as described and illustrated, it was operated at up to 100 MW(… more
Date: November 1990
Creator: Boing, L. E.; Wimunc, E. A. & Whittington, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Proposed Gamma-Ray Detection System for the Monitoring of Core Water Inventory in a Pressurized Water Reactor

Description: An initial study has been performed of the feasibility of employing an axial array of gamma detectors located outside the pressure vessel to monitor the coolant in a PWR. A one-dimensional transport analysis model is developed for the LOFT research reactor and for a mock-PWR geometry. The gamma detector response to coolant voiding in the core and down-comer has been determined for both geometries. The effects of various conditions (for example, time after shutdown, materials in the transport pa… more
Date: December 1987
Creator: Markoff, Diane Melanie
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Evaluation of Alternative Reactor Vessel Cutting Technologies for the Experimental Boiling Water Reactor at Argonne National Laboratory

Description: Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be … more
Date: December 1989
Creator: Boing, L. E.; Henley, D. R.; Manion, William J. & Gordon, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Rolling of Gold Sheet for LAPRE 2 Pressure Liner

Description: From abstract: "This report discusses a special handling procedure devised to prevent contamination of high-purity gold while processing the metal from cast billet to final sheet. Gold of 99.99% purity was cast into rectangular billets and rolled into sheet whose final dimensions were 48 by 12-1/2 by 0.015 inch...As a final step, the sheet was annealed dead-soft in preparation for subsequent forming operations."
Date: July 1958
Creator: Keil, R. W.; Hanks, G. S. & Taub, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prestressed Concrete Reactor Vessel Model 1

Description: From introduction: The goal of engineers associated with nuclear power plants is the achievement of safe plants with low generating costs.One possible means of lowering costs is to increase the power generating capability for a single generating unit. To accomplish this, the sizes of nuclear reactors have been increased.
Date: October 25, 1966
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.

Description: Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-… more
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mid-Year Summary Report October 1, 1960-March 31, 1961 Army Pwr Support and Development Program

Description: Abstract: A cyclic stress analysis of the SM-1 primary system was carried out. Problems encountered in the fabrication of PM-2A Core II and SM-lA Core II are described, and the results of an examination of damaged SM-lA Core I stationary fuel elements reported. A preliminary study of the radiation damage to SM-1 reactor vessel was made and the possibility of annealing the vessel discussed. Performance analyses are presented for five cores: SM-1 Core, SM-1 Core 1 rearranged and spiked, SM-1 Core… more
Date: June 2, 1961
Creator: Hoover, H. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 4

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nucl… more
Date: October 1, 1963
Creator: Sorlie, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 2

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuc… more
Date: April 1, 1963
Creator: Quinn, E. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 3

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nucl… more
Date: July 1, 1963
Creator: Sorlie, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW

Description: Hazard report on the Experimental Boiling Water Reactor that covers the basic modifications to the plant as designed to increase the present operating design rating of 20 Mw(t) to a new rating of 100 Mw(t). Changes and additions to the plant, core, reactor vessel, and other major components are shown. An analysis of the effects of the changes on the performance and safety of the reactor is presented.
Date: December 1959
Creator: Wimunc, E. A. & Harrer, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of the Argonne Low Power Reactor (ALPR)

Description: Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly… more
Date: May 1961
Creator: Hamer, Eberhard E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LWR Pressure Vessel Irradiation Surveillance Dosimetry Quarterly Progress Report: October-December 1979

Description: This report was compiled at the Hanford Engineering Development Laboratory operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corpoation, for the United States Department of Energy and the Nuclear Regulatory Commission, under DOE contract number DE-AC14-76FF02170 and NRC service request number TV-0176.
Date: December 1980
Creator: Guthrie, G. L. & McElroy, W. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SM-2 Full Scale Flow Studies Termination Report

Description: Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of wate… more
Date: July 30, 1961
Creator: Christenson, J. A.; Richards, W. M. S. & Davidson, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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