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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.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Some Scoping Experiments for a Space Reactor

Description: Some scoping experiments were performed to evaluate fuel performance in a lithium heat pipe reactor operating at a nominal 1500K heat pipe temperature. Fuel-coolant and fuel-coolant-clad relationships showed that once a failed heat pipe occurs temperatures can rise high enough so that large concentrations of uranium can be transported by the vapor phase. Upon condensation this uranium would be capable of penetrating heat pipes adjacent to the failed pipe. The potential for propagation of failur… more
Date: July 7, 1983
Creator: Alexander, C. A. & Ogden, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal strains in titanium aluminide and nickel aluminide composites

Description: Neutron diffraction was used to measure residual thermal strains developed during postfabrication cooling in titanium aluminide and nickel aluminide intermetallic matrix composites. Silicon carbide /Ti 14Al-21Nb, tungsten and sapphire/NiAl, and sapphire and SiC-coated sapphire/NiAl{sub 25}Fe{sub 10} composites were investigated. The thermal expansion coefficient of the matrix is usually greater than that of the fibers. As such, during cooldown, compressive residual strains are generated in the … more
Date: January 1, 1992
Creator: Saigal, A. (Tufts Univ., Medford, MA (United States). Dept. of Mechanical Engineering) & Kupperman, D.S. (Argonne National Lab., IL (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Seismic velocities and attenuation in an underground granitic waste repository subjected to heating

Description: The behavior of a granitic rock mass subjected to thermal load has been studied by an acoustic cross-hole technique between four boreholes, over a period of some two years. Velocities between boreholes were obtained from the times-of-flight of pulses of acoustic waves between transducers clamped to the borehole wall. The attenuation was obtained by a spectral ratios technique. When the heater was turned on, the velocities increased rapidly to an asymptotic value. When the heater was turned off,… more
Date: March 1, 1984
Creator: Paulsson, B.N.P. & King, M.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Test PCM-5 rod bowing and bow direction reversal. [PWR]

Description: Test PCM-5 was the first bundle test in the PCM Test Series being conducted by the Thermal Fuels Behavior Program of EG and G Idaho, Inc. as part of the Nuclear Regulatory Commission's Fuel Behavior Program. The experiment was performed in the Power Burst Facility (PBF) reactor at the Idaho National Engineering Laboratory. The bundle consisted of nine previously unirradiated PWR-type fuel rods, arranged in a 3 x 3 array within a square cross section flow shroud, with rod-to-rod spacing typical … more
Date: January 1, 1980
Creator: Kerwin, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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MHD air heater development technology. Progress report, November 26, 1979-March 31, 1980

Description: Work on the development of the directly-fired high temperature air heater (HTAH) for MHD power plants is reported. Progress is reported on three tasks: (1) materials selection, evaluation, and development, (2) operability, performance, and materials testing, and (3) full-scale design concepts. Under Task 1, efforts were carried out in several areas. Work on the computer data base for material properties was begun. Data were compiled for several HTAH materials. Materials selections for Valve Tes… more
Date: May 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal-stress analysis of a Fort St. Vrain core-support block under accident conditions

Description: A thermoelastic stress analysis of a graphite core support block in the Fort St. Vrain High Temperature Gas Cooled Reactor is described. The support block is subjected to thermal stresses caused by a loss of forced circulation accident of the reactor system. Two- and three-dimensional finite element models of the core support block are analyzed using the ADINAT and ADINA codes, and results are given that verify the integrity of this structural component under the given accident condition.
Date: January 1, 1982
Creator: Carruthers, L. M.; Butler, T. A. & Anderson, C. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Postirradiation cladding strength under biaxial loading with an increasing temperature ramp. [LMFBR]

Description: The flow behavior of unirradiated 20% cold worked AISI 316 tubing during constant pressure, increasing temperature tests was modeled with a constitutive relation approach; strain below approximately 0.2% came predominantly from an anelastic portion of the model while higher strains were predominantly plastic. The flow of cladding sections from irradiated fuel pins was largely restricted to the strain region attributed to anelastic deformation due to reduced ductility compared to unirradiated tu… more
Date: April 1, 1980
Creator: Duncan, D. R. & Hunter, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermal responses of tokamak reactor first walls during cyclic plasma burns

Description: The CINDA-3G computer code has been adapted to analyze the thermal responses and operating limitations of two fusion reactor first-wall concepts under normal cyclic operation. A component of an LMFBR computer has been modified and adapted to analyze the ablative behavior of first-walls after a plasma disruption. The first-wall design concepts considered are a forced-circulation water-cooled stainless steel panel with and without a monolithic graphite liner. The thermal gradients in the metal wa… more
Date: January 1, 1977
Creator: Smith, D. L. & Charak, I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Time-dependent behavior of concrete

Description: This paper is a condensed version of the material presented at the International Workshop on Finite Element Analysis of Reinforced Concrete, Session 4 -- Time Dependent Behavior, held at Columbia University, New York on June 3--6, 1991. Dr. P.A. Pfeiffer presented recent developments in time-dependent behavior of concrete and Professor T. Tanabe presented a review of research in Japan on time-dependent behavior of concrete. The paper discusses the recent research of time-dependent behavior of c… more
Date: January 1, 1992
Creator: Pfeiffer, P.A. (Argonne National Lab., IL (United States)) & Tanabe, Tada-aki (Nagoya Univ. (Japan). Dept. of Civil Engineering)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program: Quarterly Progress Report, January-March 1980

Description: This progress report summarizes the Argonne National Laboratory work performed during January, February, and March 1980 on water-reactor-safety problems. The research and development area covered is Transient Fuel Response and Fission-Product Release.
Date: August 1, 1980
Creator: Massey, Walter E. & Kyger, Jack A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]

Description: Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200 < Re < 800). The results provide a data base for evaluating deformation and blockage models employed with design-b… more
Date: January 1, 1982
Creator: Longest, A.W.; Chapman, R.H. & Crowley, J.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fatigue behavior of Type 316 stainless steel following neutron irradiation inducing helium

Description: Since a tokamak reactor operates in a cyclic mode, thermal stresses will result in fatigue in structural components, especially in the first wall and blanket. There has been limited work on fatigue in irradiated alloys but none on irradiated materials containing significant amounts of irradiation-induced helium. To provide scoping data and to study the effects of irradiation on fatigue behavior, 20%-cold-worked type 316 stainless steel from the MFE reference heat was studied.
Date: January 1, 1980
Creator: Grossbeck, M.L. & Liu, K.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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W-1 SLSF post-test data analysis. Part 1. Thermal hydraulic analysis. [LMFBR]

Description: Four types of tests were performed: (1) a decay heat transient test, (2) Loss-of-Piping-Integrity (LOPI) tests, (3) Boiling Window Tests (BWT), and (4) a fuel pin dryout and failure test. In addition, preliminary tests were run to check systems performance, instrumentation performance and test section heat balance. The objective of the decay heat test was to determine the decay heat transfer characteristics of fresh fuel pins with subcooled sodium. The objective of the LOPI experiments was to t… more
Date: October 1, 1980
Creator: Knight, D.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ceramic coatings on diesel engine components. Period covered: January 1979-August 1979

Description: Diesel engines with imporved thermal efficiency and fuel economy or flexibility will be required to meet automotive energy conservation goals. These goals can be met by minimizing engine heat loss to the coolant, i.e., by the use of a thermal insulating barrier on the interior surfaces of the combustion space. The development and testing of ceramic coatings for diesel engine components are discussed. These coatings include oxides of Al, Cr, Zr, Mg, Si, Ti, and Ca, and Mo and Ch carbides. Data o… more
Date: October 1, 1979
Creator: Kvernes, I & Lillerud, K P
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal stress and creep fatigue limitations in first wall design

Description: The thermal-hydraulic performance of a lithium cooled cylindrical first wall module has been analyzed as a function of the incident neutron wall loading. Three criteria were established for the purpose of defining the maximum wall loading allowable for modules constructed of Type 316 stainless steel and a vanadium alloy. Of the three, the maximum structural temperature criterion of 750/sup 0/C for vanadium resulted in the limiting wall loading value of 7 MW/m/sup 2/. The second criterion limite… more
Date: January 1, 1977
Creator: Majumdar, S.; Misra, B. & Harkness, S.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Light-water-reactor safety research program. Quarterly progress report, January-March 1981

Description: A mechanistic model for the prediction of microcracking (grain-boundary separation) during transient conditions has been generated within the context of the FASTGRASS computer code. A model based on the work of DiMelfi and Deitrich describing ductile/brittle behavior has been replaced by one based on the work of Beere and Speight, Chuang and Rice, and Chen and Argon. The theory underlying this new model is described and its proposed implementation in the prediction of DEH test results is outlin… more
Date: November 1, 1981
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermoelastic buckling of plates in a cylindrical geometry against an elastic back support. [LMFBR]

Description: A plate which is fixed at its edges to a strong edge support structure will develop large compressive stresses when heated from ambient temperature more rapidly than the support structure. Determining the response of the plate to this situation requires stability analysis to ascertain whether the plate might buckle, or whether the constrained thermal expansion will lead to compressive stresses exceeding the yield point because it did not buckle. A special case is considered here, both analytica… more
Date: January 1, 1980
Creator: Simmons, L. D. & Wierman, R. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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/sup 238/Pu fuel form processes. Quarterly report, April-June 1981

Description: An analytical program has been started to determine the cause of cracking in DOP-26 iridium alloy during welding of GPHS clad vent sets. Analyses revealed that (1) intergranular cracking in the interior weld bead occurs in the heat-affected zone adjacent to the arc quench taper and at weld edges, (2) grain surfaces exposed by cracking exhibit a characteristic ridge network topography, and (3) no elements that could cause hot shortness were detected in the ridge networks.
Date: December 1, 1981
Creator: Folger, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Mechanism Explaining the Instability of EBR-I, Mark III

Description: Presented at the International Atomic Energy Agencysponsored Seminar on the Physics of Fast and Intermediate Reactors. Vienna, August 3-11, 196l. A feedback model, was developed to account for resonant instabilities in the Mark II core. In this model, the prompt positive power coefficient effect is ascribed to fuel rod bowing and the delayed negative power coefficient effect to thermally lnduced motions in the lower shield plate. Since this model is supported by observations, it is concluded th… more
Date: September 1, 1961
Creator: Smith, R. R.; Matlock, R. G.; McGinnis, F. D.; Novick, M. & Thalgott, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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