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STATUS REVIEW OF THE KEWB PROGRAM

Description: jectives, the accomplishments, and a summary of the work outstanding. The obtectives of the experimental and analytical studies were to investigate and reach an understanding of the kinetic behavior of aqueous homogeneous reactors. Information produced by the program, experiments on the spherical core, capsule experiments, and the remaining work schedule are discussed. (W.D.M.)
Date: January 28, 1959
Creator: Flora, J. W.
Partner: UNT Libraries Government Documents Department

Monthly Progress Report for the Period August 1 to 31, 1958

Description: plants ln England and France. With the increasing de output of given designs and probably allow operation at higher polymer contents than orignally foreseen, thereby reducing the make-up requirements. The physical characteristics of the OMRE such as critical loading, temperature coefficient, and general stability appeared to be close to the predicted values. Radiation levels in the primary circuit area during full power operation appear to be so low that maintenance is possible during operation. The reactor has been run for a full month at 30% polymer concentration and is, at the time of this writing, brought to a still higher steady state percentage of breakdown products ln the coolant stream. No evidence whatsoever of fouling or precipitation has been observed. The reactor behaves in a routine manner in all respects and invites immediate application of the OMR principle to reactors for large scale ceniral stations. Final design on one 11.4 Mwe unit for the city of Piqua, Ohio, has now stanted. A short description is given of OMR power reactors. The use of magnetic jack mechanisms for control and safety rods provides a reactors top shield without penetrations, as well as an unpenetrated lower core vessel, still avoiding any interference from the control rods during fuel changing. The new finned-plate fuel element is mentioned as well as the use of a liquid pressurizing pump instead of nitrogen gas pressurization. It is conservatively predicted that the cost of organic liquid make-up for these designs will not contribute more than one half to one mill per kwh to the total power cost. In case operation at higher polymer concentrations appears practicable, this figure may even be lower. More detailed pricing informntion available now, has shown that the original cost estimate of around 0 per kw installed for a 150 Mwe plant can ...
Date: September 20, 1958
Creator: Garbe, R. W. & Walchli, H. E.
Partner: UNT Libraries Government Documents Department

STUDY OF THE FEASIBILITY OF SHIPPING THE FIRST SPENT CORE FROM ELK RIVER, MINN. TO POLICORO, ITALY. Final ReporT, August 1 to September 15, 1961

Description: A study was conducted to assess the feasibility of transporting the first spent core of the Elk River Power Reactor to Policoro, ltaly. Commercial transport arrangements were also examined and it was found that changes in indemnity and/or insurance are required. Other aspects appear favorable. (J.R.D.)
Date: September 15, 1961
Creator: Fraenkel, S.J.
Partner: UNT Libraries Government Documents Department

CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES

Description: A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A description is also included concerning 5 reactor types considered along with a discussion of the effects on power costs of varying the significant core parameters. A listing of basic references is given. (J.R.D.)
Date: January 1, 1959
Creator: Atomic Energy Commission, Washington, D.C. & Jackson and Moreland, Inc., Boston
Partner: UNT Libraries Government Documents Department

POWER REMOVAL FROM A BOILIGN REACTOR

Description: BS>This work is based on a rather specific and simplified model of the reactor core in which internal circulation exists. Because of the model simplicity, the influence varying some of the parameters appears more directly. In particular, calculation of the circulation factor, which is important in determining the need for vapor separators is included. On this basis it was felt desirable to make the results of this study available even though they have been largely superseded by the later work. (auth)
Date: October 1, 1952
Creator: Zmola, P. C. & Lawson, E. N.
Partner: UNT Libraries Government Documents Department

Iodine transport analysis in the ESBWR.

Description: A simplified ESBWR MELCOR model was developed to track the transport of iodine released from damaged reactor fuel in a hypothesized core damage accident. To account for the effects of iodine pool chemistry, radiolysis of air and cable insulation, and surface coatings (i.e., paint) the iodine pool model in MELCOR was activated. Modifications were made to MELCOR to add sodium pentaborate as a buffer in the iodine pool chemistry model. An issue of specific interest was whether iodine vapor removed from the drywell vapor space by the PCCS heat exchangers would be sequestered in water pools or if it would be rereleased as vapor back into the drywell. As iodine vapor is not included in the deposition models for diffusiophoresis or thermophoresis in current version of MELCOR, a parametric study was conducted to evaluate the impact of a range of iodine removal coefficients in the PCCS heat exchangers. The study found that higher removal coefficients resulted in a lower mass of iodine vapor in the drywell vapor space.
Date: March 1, 2009
Creator: Kalinich, Donald A.; Gauntt, Randall O.; Young, Michael Francis & Longmire, Pamela
Partner: UNT Libraries Government Documents Department

Study on severe accident fuel dispersion behavior in the Advanced Neutron Source reactor at Oak Ridge National Laboratory

Description: Core flow blockage events are a leading contributor to core damage initiation risk in the Advanced Neutron Source (ANS) reactor. During such an accident, insufficient cooling of the fuel could result in core heatup and melting under full coolant flow condition. Coolant inertia forces acting on the melt surface would likely break up the melt into small particles. Under thermal-hydraulic conditions of ANS coolant channel, micro-fine melt particles are expected. Heat transfer between melt particle and coolant, which affects particle breakup, was studied. The study indicates that the thermal effect on melt fragmentation seems to be negligible because the time corresponding to the breakup due to hydrodynamic forces is much shorter than the time for the melt surface to solidify. The study included modeling and analyses to predict transient behavior and transport of debris particles throughout the coolant system. The transient model accounts for the surface forces acting on the particle that results from the pressure variation on the surface, inertia, virtual mass, viscous force due to relative motion of particle in the coolant, gravitation, and resistance due to inhomogenous coolant velocity radially across piping due to possible turbulent coolant motions. Results indicate that debris particles would reside longest in heat exchangers because of lower coolant velocity there. Also core debris tends to move together upon melting and entrainment.
Date: December 31, 1995
Creator: Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V. & Xiang, J.Y.
Partner: UNT Libraries Government Documents Department

Consolidated Edison Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and powerdensity distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor. (J.R.D.)
Date: March 1, 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department

Fuel Element Structural Design and Manufacture for the Consolidated Edison Thorium Reactor Plant

Description: The design of the fuel-element structure for the CETR is described. Component parts of the assembly comprise the fuel-bundle assembly, the fuel-can assembly, the upper transition, the fuel-element spring, and the upper nozzle and seal assembly. (J.R.D.)
Date: September 1, 1960
Creator: Collings, D. M.; Gestson, D. K.; Andrea, C.; Ferris, H. D.; Boyer, R. L. & Larson,G. C.
Partner: UNT Libraries Government Documents Department

Studies of Reactor Containment. Task on Structural and Mechanical Design Criteria for Nuclear Reactor Containment. An Annotated Bibliography on Reactor Containment. Report No. 1

Description: A survey of recent publications concerned with structural and mechanical aspects of nuclear reactor containment was conducted during the first phase period. This report presents an annotated bibliography of 279 such publications. Many of the references listed appeared in Nuclear Science Abstracts and were published in the period from 1954 through 1957. (auth)
Date: August 1, 1958
Partner: UNT Libraries Government Documents Department