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Assessment of light water reactor fuel damage during a reactivity initiated accident

Description: This paper presents an assessment of LWR fuel damage during a reactivity initiated accident and comments on the adequacy of the present USNRC design requirements. Results from early SPERT tests are reviewed and compared with results from recent computer simulations and PBF tests. A progression of fuel rod and cladding damage events is presented. High strain rate deformation of relatively cool irradiated cladding early in the transient may result in fracture at a radial average peak fuel enthalp… more
Date: January 1, 1980
Creator: MacDonald, P. E.; Seiffert, S. L.; Martinson, Z. R.; McCardell, R. K.; Owen, D. E. & Fukuda, S. K.
Partner: UNT Libraries Government Documents Department
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Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

Description: A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Partner: UNT Libraries Government Documents Department
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X-ray measurements of stresses and defects in EFG and large grained polycrystalline silicon ribbons. First quarterly report

Description: The first model of a modified Bond goniometer has been built and tested for the precision measurement of interplanar spacings in Si-single crystals. A change in interplanar spacing ..delta..d/d approximately = to +- 10/sup -5/ can be detected which corresponds to surface stresses of the order of +- 1000 psi. A second version of the goniometer is being assembled incorporating a removable microscope for precision alignment of the Si-strip into the primary X-ray beam.
Date: January 1, 1978
Creator: Wagner, C.N.J.
Partner: UNT Libraries Government Documents Department
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Repair Welding of Fusion Reactor Components

Description: Recent experimental investigations indicate that the repair welding of irradiated materials containing greater than 1 to 2.5 appm helium leads to catastrophic cracking in the heat affected zone of the weld. The high temperatures and cooling tensile stresses which occur during the welding process lead to enhanced helium bubble growth in the heat affected zone region, resulting in catastrophic cracking upon cooling. An investigation is proposed which seeks to determine the effect of stress state … more
Date: May 20, 1992
Creator: Chin, Bryan A.
Partner: UNT Libraries Government Documents Department
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Waste Treatment and Disposal Progress Report for June and July 1961

Description: 7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scaven… more
Date: October 24, 1961
Creator: Blanco, R. E. & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Development of an extended-burnup Mark B design. First semi-annual progress report, July-December 1978. Report BAW-1532-1. [PWR]

Description: The primary objective of this program is to develop and demonstrate an improved PWR fuel assembly design capable of batch average burnups of 45,000-50,000 MWd/mtU. To accomplish this, a number of technical areas must be investigated to verify acceptable extended-burnup fuel performance. This report is the first semi-annual progress report for the program, and it describes work performed during the July-December 1978 time period. Efforts during this period included the definition of a preliminar… more
Date: October 1, 1979
Partner: UNT Libraries Government Documents Department
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Effects of flow curvature on the aerodynamics of Darrieus wind turbines

Description: A theoretical and experimental investigation was conducted which clearly showed the effects of flow curvature to be significant determinants of Darrieus turbine blade aerodynamics; qualitatively, these results apply equally to straight or curved bladed machines. Unusually large boundary layer radial pressure gradients and virtually altered camber and incidence are the phenomena of primary importance. Conformal mapping techniques were developed which transform the geometric turbine airfoils in c… more
Date: July 1, 1980
Creator: Migliore, P. G. & Wolfe, W. P.
Partner: UNT Libraries Government Documents Department
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Seal-Shell-a Digital Program to Determine Stresses and Deflections in an Axisymmetric Shell of Revolution

Description: SEAL-SRELL, a FORTRAN II program registered as code number M0077 at Bettis Atomic Power Laboratory, is written for the Philco 2000 computer with two tape units. The program is designed to determine loads, deflections, and stresses in a thin shell of revolution under axisymmetric end loads and pressure. (auth)
Date: September 1, 1961
Creator: Friedrich, C.M.
Partner: UNT Libraries Government Documents Department
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Analysis of LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step transient

Description: This report presents the analysis of the LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step thermal transient. Previous analysis performed under subcontract by Basic Technology Incorporated was utilized where applicable. The SAASIII finite element computer program was used to determine stress distributions in the nozzles due to the step transient. Computer results were then incorporated in the necessary additional calculations to ascertain that stress limitations were not ex… more
Date: January 18, 1978
Creator: Nitzel, M.E.
Partner: UNT Libraries Government Documents Department
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The rate dependence of the saturation flow stress of Cu and 1100 Al

Description: The strain-rate dependence of the saturation flow stress of OFHC Cu and 1100 Al from 10{sup {minus}3}s{sup {minus}1} to nearly to 10{sup 12}s{sup {minus}1} is examined. The flow stress above 10{sup 9}s{sup {minus}1} is estimated using Wallace's theory of overdriven shocks in metals. A transition to the power-law behavior {Psi} {approximately} {tau}{sub s}{sup 5} occurs at a strain rate of order 10{sup 5}s{sup {minus}1}. 10 refs., 2 figs.
Date: January 1, 1991
Creator: Preston, D.L.; Tonks, D.L. & Wallace, D.C.
Partner: UNT Libraries Government Documents Department
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Measurement and analysis of flow wall shear stress in an interior subchannel of triangular array rods. [LMFBR]

Description: A simulated model of triangular array rods with pitch to diameter ratio of 1.10 (as a test section) and air as the fluid flow was used to study the LMFBR hydraulic parameters. The wall shear stress distribution around the rod periphery, friction factors, static pressure distributions and turbulence intensity corresponding to various Reynolds numbers ranging from 4140 to 36170 in the central subchannel were measured. Various approaches for measurement of wall shear stress were compared. The meas… more
Date: August 1, 1977
Creator: Fakori-Monazah, M.R. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department
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EFFECT OF NEUTRON IRRADIATION ON MATERIALS SUBJECTED TO MULTI-AXIAL STRESS DISTRIBUTIONS. Quarterly Report for the Period Ending June 30, 1962

Description: Activities in a program to determine the effects of neutron irradiation on A-302B steel are reported. Plans are discussed concerning performance tests on tensile, notched tensile, tube, and Charpy specimens. An irradiation capsule design was finalized. A theoretical analysis of the critical conditions arising in a tube subjected to both internal pressure and axial load is included. (J.R.D.)
Date: August 13, 1962
Creator: Trozera, T A
Partner: UNT Libraries Government Documents Department
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PNL technical review of pressurized thermal-shock issues. [PWR]

Description: Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the Nuclear Regulatory Commission (NRC) should adopt regarding the ability of reactor pressure vessels to withstand the effects of pressurized thermal shock (PTS). Licensees of eight pressurized water reactors provided NRC with estimates of remaining effective full power years before corrective actions would be required to prevent an unsafe operating condition. PNL reviewed these responses and the r… more
Date: July 1, 1982
Creator: Pedersen, L. T.; Apley, W. J.; Bian, S. H.; Defferding, L. J.; Morgenstern, M. H.; Pelto, P. J. et al.
Partner: UNT Libraries Government Documents Department
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Inelastic processes in seismic wave generation by underground explosions

Description: Theories, computer calculations, and measurements of spherical stress waves from explosions are described and compared, with emphasis on the transition from inelastic to almost-elastic relations between stress and strain. Two aspects of nonspherical explosion geometry are considered: tectonic strain release and surface spall. Tectonic strain release affects the generation of surface waves; spall closure may also. The reduced-displacement potential is a common solution (the equivalent elastic so… more
Date: August 1, 1980
Creator: Rodean, H.C.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962

Description: The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedepe… more
Date: October 10, 1962
Creator: Weinstein, D. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 1, September 15, 1961 to December 14, 1961

Description: A research program to determine the extent to which Zr and Zircaloy-2 exhibits delayed fnilure (static fatigue) as caused by absorbed H/sub 2/ and applied stress is outlined. Dynamic tensile tests were carried out on Zr and Zircaloy-2 without and wlth 200 ppm H/sub 2/. Preliminary results of a delayed failure investigation suggest that Zr containing 200 ppm H/sub 2/ is relatively insensitive to delayed ailure at room temperature up to 900 hr. (D.L.C.)
Date: January 1, 1962
Partner: UNT Libraries Government Documents Department
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Effects of Temperature on Mechanical Properties of Normal Uranium Dingot

Description: Fatigue properties of normal uranium dingot for rotating beam specimens between 150 and 600 deg C are shown as S-N diagrams and are also given by an empirical equation of the form S = bN/sub m/, where S is the stress, N the number of cycIes, and b and m temperature dependent parameters. Tensile properties for temperatures ranging from 30 to 700 deg C are presented in tabular form and as stress-strain diagrams. All of the properties were found to decrease in value with increasing temperature exc… more
Date: January 1, 1962
Creator: Pederson, K. & Murphy, G.
Partner: UNT Libraries Government Documents Department
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Geotechnical studies relevant to the containment of underground nuclear explosions at the Nevada Test Site

Description: The Department of Energy and the Department of Defense are actively pursuing a program of nuclear weapons testing by underground explosions at the Nevada Test Site (NTS). Over the past 11 years, scores of tests have been conducted and the safety record is very good. In the short run, emphasis is put on preventing the release of radioactive materials into the atmosphere. In the long run, the subsidence and collapse of the ground above the nuclear cavities also are matters of interest. Currently,… more
Date: May 1, 1982
Creator: Heuze, F.E.
Partner: UNT Libraries Government Documents Department
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