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Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor Materials Test 2

Description: A loss-of-coolant accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects on pressurized water reactor (PWR) test fuel bundles. This Experiment Operation Plan (EOP) Addendum 2, together with the referenced EOP, describes the desired operating conditions and additional hazards review associated with the four-part MT-2 experiment. The primary portions of the experiment, MT-2.2 and MT-2.3, will evaluate the following: 1) the mechanical deformation of pressuriz… more
Date: September 1, 1981
Creator: Russcher, G. E.; Barner, J. O.; Hesson, G. M.; Wilson, C. L.; Parchen, L. J.; Cunningham, M. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Beginning-of-Life Data Report for the Instrumented Fuel Assembly (IFA)-527

Description: This report presents beginning-of-life (BOL) data from the first four months of operation of the six-rod instrumented fuel assembly (IFA)-527 in the Halden Boiling Water Reactor (HBWR), Halden, Norway. This assembly is the last in a series of U.S. Nuclear Regulatory Commission (NRC)-sponsored tests to verify steady-state fuel performance computer codes. IFA-527 contains five identical rods with high-density stable fuel pellets and 0.23-mm diametral gaps and one rod with similar fuel pellets but… more
Date: September 1, 1981
Creator: Lanning, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL PERFORMANCE IMPROVEMENT PROGRAM Power-Ramp Testing and Postirradiation Examination of PCI- Resistant LWR Fuel Rod Designs

Description: This report describes the power-ramp testing results from 10 fuel rods irradiated in the Halden Boiling Water Reactor (HBWR), Halden, Norway. Tne work is part of the Fuel Performance Improvement Program (FPIP), which is sponsored by the U.S. Department of Energy (DUE) and is conducted through the joint efforts of Consumers Power Company, Exxon Nuclear Company, lnc., and Pacific Northwest Laboratory. The objective of the FPlP is to identify and demonstrate fuel concepts with improved pellet-clad… more
Date: September 1, 1982
Creator: Barner, J. O. & Guenther, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PARAMETRIC REACTIVITY TRANSIENT ANALYSES FOR THE FFTF NUCLEAR PROOF TEST REACTOR

Description: Fault tree techniques have been used to identify possible failure paths within the NPTR which could lead to core disassembly. The analysis o f the various faults has led to formulation of design requirements, protective system requirements, and administrative restraints required to prevent accidents from these faults. Transient analyses were performed using the heat transfer-nuclear kinetics codes, Nutiger-II, FORE-II, and MELT-II . To verify results, intercomparison studies were made between t… more
Date: January 1, 1970
Creator: Schade, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Burnup Effects Program A State-of-the-Technology Assessment

Description: Various analytical models and empirical correlations describing the fission gas release phenomenon were examined. An evaluation was made of the current pertinent experimental data on the subject of high burnup fission gas release. Data reported by individual investigators were compared and evaluated in relation to their applicability to the content and scope of the High Burnup Effects Program. These evaluations then form the bases for defining the data needs, and the selection of variables to b… more
Date: June 1, 1982
Creator: Rising, K. H.; Bradley, E. R.; Williford, R. E. & Freshley, M D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST FLUX TEST FACILITY CONCEPTUAL COMPONENT DESIGN DISCRIPTION FOR THE REACTOR NUCLEAR CONTROL COMPONENTS No. 33

Description: This document describes the nuclear control component of the Fast Test Reactor (FTR) . The Fast Test Reactor is t he central test bed of the Fast Flux Test Facility (FFTF). The Reactor Nuclear Control Components described in this document consist of neutron absorbing elements which are moved axially into and out of the general area of the active portion of the core. The electromechanical drive housings are mounted on the reactor cover and are part of the pressure boundary of the vessel and cove… more
Date: October 1, 1969
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REACTOR PHYSICS QUARTERLY REPORT JANUARY, FEBRUARY, MARCH 1970

Description: The objective of the Reactor Physics Quarterly Report is to inform the scientific community in a timely manner of the technical progress made on the many phases of reactor physics work within the laboratory. The report contains brief technical discussions of accomplishments in all areas where significant progress has been made during the quarter.
Date: May 1, 1970
Creator: Schmid, L. C.; Clayton, E. D. & Heineman, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prototypic Thermal-Hydraulic Experiment in NRU to Simulate Loss-of-Coolant Accidents

Description: Quick-look test results are reported for the initial test series of the Loss-of-Coolant Accident (LOCA) Simulation in the National Research Universal {NRU) test program, conducted by Pacific Northwest Laboratory (PNL) for the U.S. Nuclear Regulatory Commission (NRC). This test was devoted to evaluating the thermal-hydraulic characteristics of a full-length light water reactor (LWR) fuel bundle during the heatup, reflood, and quench phases of a LOCA. Experimental results from 28 tests cover refl… more
Date: April 1, 1981
Creator: Mohr, C. L.; Hesson, G. M.; Russcher, G. E.; Marsh, R. K.; King, L. L.; Wildung, N. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PAR Loop Schedule Review

Description: The status of the overall design, fabrication, and installation of the component items of the PAR loop experiment in the ORR is reviewed.
Date: January 15, 1958
Creator: Schaffer, Jr. & W.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PAR Loop Schedule Review

Description: The schedule for the installation of the PAR slurry loop experiment in the South Facility of the ORR has been reviewed and revised. The design, fabrication, and installation is approximately two weeks behind schedule at this time due to many factors; however, indications are that this time can be made up. Design is estimated to be 56 per cent complete, fabrication 27 per cent complete-and installation 11 per cent complete:
Date: March 31, 0958
Creator: Schaffer, Jr. & W.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Safety Research Programs

Description: This document summarizes the work performed by Pacific Northwest laboratory from October 1 through December 31, 1979, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary syst… more
Date: August 1, 1980
Creator: Dotson, CW
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tests on Models of Nuclear Reactor Elements - Studies of Diffusion

Description: To estimate the distribution of temperature in the proposed nuclear reactor, one must determine a coefficient of eddy diffusivity and devise a suitable method of computing the heat transfer. Measurements of diffusion in a model of a blanket element for the proposed reactor indicated a gross eddy diffusion coefficient of about 0.002 (? .0005) ft{sup 2}/sec. Thus, the apparent eddy diffusion for the test conditions is about 200 times the molecular diffusivity of water and about. twice that of the… more
Date: March 1, 1957
Creator: McNown, J. S.; Yih, C. S.; Yagle, R. A.; O&#x27 & Dell, W. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST FLUX TEST FACILITY CONCEPTUAL FACILTY DESIGN DESCRIPTION FOR THE INERT GAS CELL EXAMINATION FACILITY NO. 71

Description: The purpose of this Conceptual Facility Design Description (CFDD) is to provide a technical description of the Inert Gas Cell Examination Facility such that agreement with RDT on a Conceptual Design can be reached . The CFDD also serves to establish a common understanding of the facility concept among all responsible FFTF Project parties including the Architect Engineer and Reactor Designer. Included are functions and design requirements, a physical description of the facility, safety considera… more
Date: December 12, 1968
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A New 2D-Transport, 1D-Diffusion Approximation of the Boltzmann Transport equation

Description: The work performed in this project consisted of the derivation, implementation, and testing of a new, computationally advantageous approximation to the 3D Boltz- mann transport equation. The solution of the Boltzmann equation is the neutron flux in nuclear reactor cores and shields, but solving this equation is difficult and costly. The new “2D/1D” approximation takes advantage of a special geometric feature of typical 3D reactors to approximate the neutron transport physics in a specific (ax- … more
Date: June 17, 2013
Creator: Larsen, Edward
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST FLUX TEST FACILITY MONTHLY INFORMAL TECHNICAL PROGRESS REPORT MAY 1969

Description: This report was prepared by Battelle-Northwest under Contract No. AT(45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during May 1969 .
Date: June 6, 1969
Creator: Astley, E. R. & Cabell, C. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tests on Models of Nuclear Reactor Elements - Head Losses in Core Sub-Assemblies

Description: Losses have been determined for flow through models of various proposed core sub-assemblies as part of a study of the elements of a nuclear reactor. Six core sections and two? axial blanket sub-assemblies have been compared on the basis of drop in piezometric. head or pressure drop. The core sub-assemblies are composed of an entrance nozzle, a lower axial blanket section, the core section, an upper axial blanket section, and a short section for the handling lug. The four parts of the sub-assemb… more
Date: July 1, 1957
Creator: McNown, J. S.; Yagle, R. A. & Spengos, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Credible Accidents for Argonaut Reactors

Description: Five areas of potential accidents have been evaluated for the Argonaut-UTR reactors. They are: • insertion of excess reactivity • catastrophic rearrangement of the core • explosive chemical reaction • graphite fire • fuel-handling accident. A nuclear excursion resulting from the rapid insertion of the maximum available excess reactivity would produce only 12 MWs which is insufficient to cause fuel melting even with conservative assumptions. Although precise structural rearrangement of the core … more
Date: April 1, 1981
Creator: Hawley, S. C.; Kathern, R. L. & Robkin, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor Materials Tests 1 and 2

Description: A loss of Coolant Accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects of LOCA conditions on pressurized water reactor test fuel bundles. This experiment operation plan for the second and third experiments of the program will provide peak fuel cladding temperatures of up to 1172K (1650{degree}F) and 1061K (1450{degree}) respectively. for a long enough time to cause test fuel cladding deformation and rupture in both. Reflood coolant delay times and the re… more
Date: September 1, 1981
Creator: Russcher, G. E.; Wilson, C. L.; Marshall, R, K.; King, L. L.; Parchen, L. J.; Pilger, J. P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity Initiated Accident Test Series Test RIA 1-2 Experiment Operating Specification

Description: This document describes the experiment operating specifications for the Reactivity Initiated Accident (RIA) Test RIA 1-2 to be conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The RIA Series I research objectives are to determine fuel failure thresholds, modes and consequences as functions of enthalpy insertion, irradiation history, and fuel design. Coolant conditions of pressure, temperature, and flow rate that are typical of hot-startup conditions in c… more
Date: July 1, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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