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Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, December 1, 1979-February 29, 1980

Description: Information is presented concerning bundle geometry with wrapped and bare rods; LMFBR outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.
Date: January 1, 1980
Creator: Todreas, N.E.; Golay, M.W. & Wolf, L.
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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Turbulent interchange in triangular array bare rod bundles

Description: Bulk mixing coefficients were measured for single plane water flow in a simulated rod bundle with a pitch to diameter ratio of 1.10. A tracer technique employing Rhodamine B as the tracer and measuring fluorescence was used. Isokinetic sampling was achieved by using a pressure balance method. The results were corrected for both entrance effects and diversion crossflows. The results showed a change in Reynolds number behavior as the laminar sublayer began to ''choke'' the turbulent mixing. This,… more
Date: July 1, 1977
Creator: Kelly, J.M. & Todreas, N.
Partner: UNT Libraries Government Documents Department
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Hydrodynamic behavior of a bare rod bundle. [LMFBR]

Description: The temperature distribution within the rod bundle of a nuclear reactor is of major importance in nuclear reactor design. However temperature information presupposes knowledge of the hydrodynamic behavior of the coolant which is the most difficult part of the problem due to complexity of the turbulence phenomena. In the present work a 2-equation turbulence model--a strong candidate for analyzing actual three dimensional turbulent flows--has been used to predict fully developed flow of infinite … more
Date: June 1, 1977
Creator: Bartzis, J.G. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department
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Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, September 1, 1979-November 30, 1979

Description: Information is presented concerning bundle geometry with wrapped and bare rods; subchannel geometry with bare rods; LMFBR outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.
Date: January 1, 1979
Creator: Todreas, N.E.; Golay, M.W. & Wolf, L.
Partner: UNT Libraries Government Documents Department
open access

Laboratory manual for salt-mixing test in 37- and 217-pin bundles. [LMFBR]

Description: This laboratory manual deals with the procedure employed during salt tracer experiments used in evaluating the hydraulic characteristics of a rod bundle. A description of the standard equipment used is given together with the details of manufacture of probes used for detecting the salt concentration. Details of the bundle construction have been excluded as they are availble in the reference cited. An attempt has been made to point out potential trouble areas and procedures.
Date: August 1, 1980
Creator: Chan, Y.N. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department
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MIT LMFBR blanket physics project progress report No. 7, July 1, 1975--September 30, 1976

Description: Work during the period was devoted primarily to a range of analytical/numerical investigations, including evaluation of means to improve external blanket designs, beneficial attributes of the use of internal blankets, improved methods for the calculation of heterogeneous self-shielding and parametric studies of calculated spectral indices. Experimental work included measurements of the ratio of U-238 captures to U-235 fissions in a standard blanket mockup, and completion of development work on … more
Date: September 30, 1976
Creator: Driscoll, M.J. (ed.)
Partner: UNT Libraries Government Documents Department
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Resonance region neutronics of unit cells in fast and thermal reactors

Description: A method has been developed for generating resonance-self-shielded cross sections based upon an improved equivalence theorem, which appears to allow extension of the self-shielding-factor (Bondarenko f-factor) method, now mainly applied to fast reactors, to thermal reactors as well. The method is based on the use of simple prescriptions for the ratio of coolant-to-fuel region-averaged fluxes, in the equations defining cell averaged cross sections. Linearization of the dependence of these functi… more
Date: May 1, 1977
Creator: Salehi, A. A.; Driscoll, M. J. & Deutsch, O. L.
Partner: UNT Libraries Government Documents Department
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Input parameters to codes which analyze LMFBR wire-wrapped bundles

Description: This report provides a current summary of recommended values of key input parameters required by ENERGY code analysis of LMFBR wire wrapped bundles. This data is based on the interpretation of experimental results from the MIT and other available laboratory programs.
Date: December 1, 1980
Creator: Hawley, J.T.; Chan, Y.N. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department
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Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, March 1, 1977--May 31, 1977

Description: Progress is summarized in the following tasks: (1) bundle flow studies (wrapped and bare rods); (2) subchannel flow studies (bare rods); (3) LMFBR outlet plenum flow mixing; and (4) theoretical determination of local temperature fields in LMFBR fuel rod bundles. (DG)
Date: January 1, 1977
Creator: Todreas, N.E.; Golay, M.W. & Wolf, L.
Partner: UNT Libraries Government Documents Department
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MIT LMFBR Blanket Research Project. Quarterly progress report, January 1-March 31, 1980

Description: During FY 1980 work is being carried out on the following subtasks: evaluation of the thermal/hydraulic/mechanical consequences of enhanced fertile and fissile capture rates at interfaces; development of simpler ways to estimate interface capture rate enhancement; particularization of the breed/burn internal/external blanket management scheme; and participation in the Large Core Code Evaluation Working Group (LCCEWG) program.
Date: May 31, 1980
Creator: Driscoll, M.J.
Partner: UNT Libraries Government Documents Department
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Fluid-mixing studies in a hexagonal 217-pin wire-wrapped rod bundle. [LMFBR]

Description: Mixing, pressure drop, and flow split experiments were performed on a 217 pin LMFBR fuel bundle with a pitch to diameter ratio of 1.25 and a lead length of 12 inches. It was found that the turbulent flow data could best be characterized by the energy parameter C/sub 1L/=.106, which is 9% higher than the value from the correlation of Chiu et al. Chiu's correlation was developed on a data base of 61 and 91 pins. The spread of existing data about the correlation is +- 25%, but the error band on ou… more
Date: February 1, 1981
Creator: Symolon, P.D. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department
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MIT LMFBR blanket research project. Final summary report

Description: This is a final summary report on an experimental and analytical program for the investigation of LMFBR blanket characteristics carried out at MIT in the period 1969 to 1983. During this span of time, work was carried out on a wide range of subtasks, ranging from neutronic and photonic measurements in mockups of blankets using the Blanket Test Facility at the MIT Research Reactor, to analytic/numerical investigations of blanket design and economics. The main function of this report is to serve … more
Date: August 1, 1983
Creator: Driscoll, M.J.
Partner: UNT Libraries Government Documents Department
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Multicell slug flow heat transfer analysis of finite LMFBR bundles

Description: An analytical two-dimensional, multi-region, multi-cell technique has been developed for the thermal analysis of LMFBR rod bundles. Local temperature fields of various unit cells were obtained for 7, 19, and 37-rod bundles of different geometries and power distributions. The validity of the technique has been verified by its excellent agreement with the THTB calculational result. By comparing the calculated fully-developed circumferential clad temperature distribution with those of the experime… more
Date: December 1, 1978
Creator: Yeung, M. K. & Wolf, L.
Partner: UNT Libraries Government Documents Department
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Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, September 1, 1978--November 30, 1978

Description: Information is presented concerning coolant mixing in LMFBR fuel rods in wrapped and bare bundle geometry; LMFBR outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.
Date: January 1, 1978
Creator: Todreas, N.E.; Golay, M.W. & Wolf, L.
Partner: UNT Libraries Government Documents Department
open access

Fabrication details for wire wrapped fuel assembly components. [LMFBR]

Description: Extensive hydraulic testing of simulated LMFBR blanket and fuel assemblies is being carried out under this MIT program. The fabrication of these test assemblies has involved development of manufacturing procedures involving the wire wrapped pins and the flow housing. The procedures are described in detail in the report.
Date: September 1, 1978
Creator: Bosy, B.J.
Partner: UNT Libraries Government Documents Department
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Interfacial effects in fast reactors. [LMFBR]

Description: The problem of increased resonance capture rates near zone interfaces in fast reactor media has been examined both theoretically and experimentally. An interface traversing assembly was designed, constructed and employed to measure U-238 capture rates near th blanket--reflector interface in the MIT Blanket Test Facility. Prior MIT experiments on a thorium--uranium interface in a blanket assembly were also reanalyzed. Extremely localized fertile capture rate increases of on the order of 50% were… more
Date: May 1, 1979
Creator: Saidi, M.S. & Driscoll, M.J.
Partner: UNT Libraries Government Documents Department
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Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Final report

Description: This project principally undertook the investigation of the thermal hydraulic performance of wire wrapped fuel bundles of LMFBR configuration. Results obtained included phenomenological models for friction factors, flow split and mixing characteristics; correlations for predicting these characteristics suitable for insertion in design codes; numerical codes for analyzing bundle behavior both of the lumped subchannel and distributed parameter categories and experimental techniques for pressure v… more
Date: August 1, 1984
Creator: Todreas, N.E.; Cheng, S.K. & Basehore, K.
Partner: UNT Libraries Government Documents Department
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MIT LMFBR blanket research project. Quarterly progress report, April 1-June 30, 1979

Description: In designing a plutonium-uranium core with thorium internal blankets there are several parameters that must be investigated to identify the design with the best performance. Choices include: the amount of moderation in the blanket, whether moderation is incorporated from the outset or added after an assembly is shuffled to the external blanket, and the cycle length both for the core and internal blanket assemblies. To investigate the effect of these parameters several core and blanket burnup an… more
Date: July 25, 1979
Creator: Driscoll, M.J.
Partner: UNT Libraries Government Documents Department
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A semi-experimental nodal synthesis method for the on-line reconstruction of three-dimensional neutron flux-shapes and reactivity

Description: The safety and optimal performance of large, commercial, light-water reactors require the knowledge at all time of the neutron-flux distribution in the core. In principle, this information can be obtained by solving the time-dependent neutron diffusion equations. However, this approach is complicated and very expensive. Sufficiently accurate, real-time calculations (time scale of approximately one second) are not yet possible on desktop computers, even with fast-running, nodal kinetics codes. A… more
Date: December 10, 1991
Creator: Jacqmin, R. P.
Partner: UNT Libraries Government Documents Department
open access

Aspects of Tokamak toroidal magnet protection

Description: Simple but conservative geometric models are used to estimate the potential for damage to a Tokamak reactor inner wall and blanket due to a toroidal magnet field collapse. The only potential hazard found to exist is due to the MHD pressure rise in a lithium blanket. A survey is made of proposed protection methods for superconducting toroidal magnets. It is found that the two general classifications of protection methods are thermal and electrical. Computer programs were developed which allow th… more
Date: July 1, 1979
Creator: Green, R.W. & Kazimi, M.S.
Partner: UNT Libraries Government Documents Department
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