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in subjects: "21 Specific Nuclear Reactors And Associated Plants"  
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Oxygen suppression in boiling water reactors. Quarterly report 2, January 1--March 31, 1978

Description: Boiling water reactors (BWR's) generally use high purity, no-additive feedwater. Primary recirculating coolant is neutral pH, and contains 100 to 300 ppB oxygen and stoichiometrically related dissolved hydrogen. However, oxygenated water increases austenitic stainless steel susceptibility to intergranular stress-corrosion cracking (IGSCC) when other requisite factors such as stress and sensitization are present. Thus, reduction or elimination of the oxygen in BWR water may preclude crackin… more
Date: October 1, 1978
Creator: Burley, E. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Theory and application of a quasi-Eulerian fluid element for the STRAW code. [LMFBR]

Description: Two-dimensional finite-element models for the treatment of the nonlinear, transient response of fluids and structures are described. The fluid description is quasi-Eulerian, so that the mesh can move independently of the material, and it includes a new finite-element upwinding scheme. The structural description is based on a corotational formulation in which the coordinate system is embedded in the elements, which is applicable to arbitrarily large rotations. The interface between the fluid and… more
Date: October 1, 1978
Creator: Kennedy, J. M. & Belytschko, T. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of FFTF startup program and future FFTF utilization

Description: A brief FFTF project description is provided which includes general plant siting information, general layout, plant design parameters, description of principal systems and components, and description of support facilities. The current status of the FFTF project is provided, including status of plant construction, overall status of the plant checkout and test program, status of operating authorization and plant operating procedures and personnel, and status of reactor core components and experim… more
Date: October 1, 1978
Creator: Hard, E. N.; Bliss, R. J. & Olson, O. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analysis of beryllium parts for cosmos 954

Description: Operation Morning Light was conducted to search for the reactor core of Cosmos 954, the nuclear-powered Soviet satellite that crashed in the northwest territories of Canada in late January 1978. many of the satellite parts found were beryllium. This study discusses the geometry, condition, microstructure, and possible fabrication history of these beryllium parts.
Date: October 25, 1978
Creator: Hanafee, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FX2-TH: A Two-Dimensional Nuclear Reactor Kinetics Code With Thermal-Hydraulic Feedback

Description: FX2-TH is a two-dimensional, time-dependent nuclear reactor kinetics program with thermal and hydraulic feedback. The neutronics model used is multigroup neutron diffusion theory. The following geometry options are available: x, r, x-y, r-z, theta-r, and triangular. FX2-TH contains two basic thermal and hydraulic models: a simple adiabatic fuel temperature calculation, and a more detailed model consisting of an explicit representation of a fuel pin, gap, clad, and coolant. FX2-TH allows feedbac… more
Date: October 1, 1978
Creator: Shober, R. A.; Daly, T. A. & Ferguson, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Alternative oxide fuel pellet fabrication for irradiation testing. [LMFBR]

Description: Fabrication of experimental breeder reactor fuel pellets by the common cold-press-and-sinter technique for irradiation testing in EBR-II is discussed. Fuel types include mixed thoria-plutonia, UO/sub 2/ enriched with 22 weight percent /sup 233/U in U, UO/sub 2/ enriched with thirty-four weight percent /sup 235/U in U, and mixed urania-plutonia.
Date: October 27, 1978
Creator: Rasmussen, D. E.; Jentzen, W. R. & McCord, R. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Heat transfer from internally-heated molten UO/sub 2/ pools. [PWR; BWR]

Description: Experimental measurements of heat transfer from internally heated pools of molten UO/sub 2/ have been obtained for two cell sizes: 10 cm x 10 cm and 20 cm x 20 cm. The experiments with the large cell have supported a previous conclusion from early small data that the measured downward heat fluxes are higher than would be expected on the basis of considerations of thermal convection. A convective model underpredicts the downward heat fluxes by a factor of 2.5 to 4.5 for all but one early experim… more
Date: October 10, 1978
Creator: Stein, R. P.; Baker, L., Jr.; Gunther, W. H. & Cook, C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

HTGR Generic Technology Program. Safety, systems and component design and development. Quarterly progress report for the period ending September 30, 1978

Description: The work documented includes HTGR safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs and under postulated accident conditions. Also included are the design, analysis, and testing of the PCRV, liner, penetrations, thermal barrier, reactor internals, steam generator, core auxiliary heat exchanger, and rotating machinery. Design studies and analyses plus experimental procedures and results are discussed and, where app… more
Date: October 1, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fatigue life of LOFT reactor vessel components

Description: This report provides calculated LOCE lifetimes of the LOFT reactor vessel components. For each component, lifetime is defined as the greatest number of LOCE transient cycles and/or other non-LOCE transient cycles such that cumulative usage factor does not exceed 1.0. The results are presented in tabular form. The results indicate that transients other than LOCE transients govern with or instead of LOCE transients for some components. The other transients are shown in the results.
Date: October 31, 1978
Creator: Kido, C. & Murdock, S.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Inspection techniques and processes for controlling FFTF fuel quality

Description: Reliable performance of fuels for the Fast Flux Test Facility (FFTF) is of paramount importance for the FFTF program. Improved inspection techniques and processes are essential for controlling the quality of such fuels. Several considerations necessitated the development and application of improved inspection techniques and processes. These include fuel design, throughput rate, and pre-irradiation characterization requirements. Some of the more significant advances are in the areas of fuel pell… more
Date: October 18, 1978
Creator: Powers, H. G.; Kirchner, T. L.; McLemore, D. R. & Gottschalk, G. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

MgO insulated coaxial instrument cable development for FFTF in-vessel temperature and voltage conditions

Description: MgO insulated nuclear instrument cable designed for use in the Fast Flux Test Facility or breeder reactor in-vessel service environments were successfully tested to temperatures to 650/sup 0/C. Breakdown Pulse Noise (BPN) thresholds in excess of 800 Vdc at 650/sup 0/C were achieved on the bulk cable; cable resistivities at 650/sup 0/C were 10/sup 8/ ft. The effect of 1000/sup 0/C annealing was a minimal reduction of cable resistivity with no observed effect on BPN threshold. No differences in i… more
Date: October 1, 1978
Creator: Chan, A. I. Y. & Cannon, C. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of the design concepts for a high fluence fast pulse reactor (HFFPR)

Description: The report describes progress that has been made on the design of a High Fluence Fast Pulse Reactor (HFFPR) through the end of calendar year 1977. The purpose of this study is to present design concepts for a test reactor capable of accommodating large scale reactor safety tests. These concepts for reactor safety tests are adaptations of reactor concepts developed earlier for DOE/OMA for the conduct of weapon effects tests. The preferred driver core uses fuel similar to that developed for Sandi… more
Date: October 1, 1978
Creator: Philbin, J. S.; Nelson, W. E. & Rosenstroch, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

Description: The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Tec… more
Date: October 1, 1978
Creator: Boegli, J. S.; Bellamy, R. R.; Britz, W. L. & Waterfield, R. L. (eds.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safety margins associated with containment structures under dynamic loading. [BWR Mark I]

Description: A technical basis for assessing the true safety margins of containment structures involved with MARK I boiling water reactor reevaluation activities is presented. It is based on the results of a plane-strain, large displacement, elasto-plastic, finite-element analysis of a thin cylindrical shell subjected to external and internal pressure pulses. An analytical procedure is presented for estimating the ultimate load capacity of the thin shell structure, and subsequently, for quantifying the desi… more
Date: October 30, 1978
Creator: Lu, S.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experiment predictions of LOFT reflood behavior using the RELAP4/MOD6 code. [PWR]

Description: The RELAP4/MOD6 computer code was used to predict the thermal-hydraulic transient for Loss-of-Fluid Test (LOFT) Loss-of-Coolant Accident (LOCA) experiments L2-2, L2-3, and L2-4. This analysis will aid in the development and assessment of analytical models used to analyze the LOCA performance of commercial power reactors. Prior to performing experiments in the LOFT facility, the experiments are modeled in counterpart tests performed in the nonnuclear Semiscale MOD 1 facility. A comparison of the… more
Date: October 16, 1978
Creator: Lin, J. C.; Kee, E. J.; Grush, W. H. & White, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fuel performance improvement program. Quarterly/annual progress report, October 1977--September 1978. [BWR; PWR]

Description: This quarterly/annual report reviews and summarizes the activities performed in support of the Fuel Performance Improvement Program (FPIP) during Fiscal Year 1978 with emphasis on those activities that transpired during the quarter ending September 30, 1978. Significant progress has been made in achieving the primary objectives of the program, i.e., to demonstrate commercially viable fuel concepts with improved fuel - cladding interaction (FCI) behavior. This includes out-of-reactor experiments… more
Date: October 1, 1978
Creator: Crouthamel, C.E. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final report on MIT contract on fuel-coolant interactions

Description: The work of this contract has yielded results in three areas which can be summarized as follows. The existing body of molten metal/water interaction data appears consistent with the criteria of the spontaneous nucleation theory. The observed fragmentation of UO/sub 2/ can be satisfactorily predicted using the proposed thermal stress initiated fracture model. The work potential of a hypothetical fuel vapor source acting on a sodium slug can be reduced by about a factor of two by considering entr… more
Date: October 1, 1978
Creator: Todreas, N E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

NSSS capital costs for a mature LMFBR industry

Description: The conceptual design of a commercial LMFBR (Target Plant) and its NSSS capital cost have been developed in support of the United Engineers and Constructors Contract EN-78-C-02-4954 with the Department of Energy. The objective of this work is to provide the Department of Energy/Office of Program Planning and Analysis - Nuclear Energy Programs with periodic updates of technical, capital cost, fuel cycle cost, and operating and maintenance cost information. This effort supports Task 3B of the UE … more
Date: October 23, 1978
Creator: Zaman, Shakir U.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Control of radionuclide transport in sodium-cooled reactor primary circuits

Description: In order to be economically viable, sodium-cooled reactors must operate at fairly high temperatures (500/sup 0/C) and with long, uninterrupted fuel cycles. These conditions increase the potential for radioactive corrosion product transport; achieving the goal of long uninterrupted fuel cycles means that release and transport of fission products from breached fuel pins will undoubtedly have to be controlled. This ppaper shows that control of radioactive material transport is an achievable goal.
Date: October 1, 1978
Creator: Brehm, W. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Costs of regulatory compliance: categories and estimating techniques.

Description: Use of the categorization scheme and cost estimating approaches presented in this report can make cost estimates of regulation required compliance activities of value to policy makers. The report describes a uniform assessment framework that when used would assure that cost studies are generated on an equivalent basis. Such normalization would make comparisons of different compliance activity cost estimates more meaningful, thus enabling the relative merits of different regulatory options to be… more
Date: October 1, 1978
Creator: Schulte, S.C.; McDonald, C.L.; Wood, M.T.; Cole, R.M. & Hauschulz, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary evaluation of alternative fuel cycle options utilizing fast breeders

Description: Various ''alternative'' fuel cycles have been proposed to alleviate concerns about reactor fuel being diverted for the manufacture of nuclear weapons. This report addresses the impact of such fuel cycles on the performance of the classical (homogeneous) oxide-fueled Liquid Metal Fast Breeder Reactor. The primary fuel cycle analyzed is the /sup 233/U//sup 238/U//sup 232/Th fuel cycle in which the fissile component /sup 233/U is ''denatured'' with /sup 238/U in order to restrict the use of reacto… more
Date: October 1, 1978
Creator: Burns, T.J. & White, J.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Unified creep-plasticity model for structural metals at high temperature. [LMFBR]

Description: A constitutive theory for use in high-temperature structural analysis of breeder reactor components is presented. It is unified in the sense that plastic and creep strains are considered to arise from similar physical mechanisms. The theory is presented in multiaxial terms along with a discussion of its underlying assumptions, its relationship to other theories and the experimental observations upon which it is based and is intended to model. The results of an extensive parameter sensitivity st… more
Date: October 1, 1978
Creator: Robinson, D. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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