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CRITICAL CONCENTRATIONS FOR HRT-TYPE REACTORS SUBJECTED TO VARIOUS CONDITIONS

Description: BS>Critical concentration calculations were made for several D/sub 2/O-H/ sub 2/O moderated HRT-type reactors with 30- and 28-in. core diameters and pressure vessel diameters of 60 and 54 in. A core temperature of 300 C was assumed for all cases while the blanket temperatures assumed the values 250, 280, and 300 C. The assumed moderator compositions were 80, 90, and 100% D/sub 2/O. (auth)
Date: February 1, 1959
Creator: Chalkley, R.
Partner: UNT Libraries Government Documents Department

BRIC-AN IBM-704 TWO-DIMENSIONAL NUCLEAR-THERMAL DEPLETION PROGRAM WITH DISTRIBUTED VOID EFFECTS

Description: BRIC is a two-dimensional nuclear-thermal depletion program to study the effects of moderator boiling on the neutron flux distribution and the depletion of the timedependent isotopes. The program requires an IBM-704 with a memory of 32,768 words and ten tape units. (auth)
Date: January 1, 1961
Creator: Jacobi, W.M.; Lawton, T.J.; Meanor, S.H. & Parrette, J.R.
Partner: UNT Libraries Government Documents Department

PRELIMINARY REPORT ON HEAT GENERATION AND STRESSES IN THE WALL OF A SPHERICAL HRE-4 PRESSURE VESSEL

Description: The heat geueration and thermal stresses in spherical HRE-4 vessels 3 to 4 1/2 ft in diameter with clad and solid stainless steel walls were invegtigated. Parameters included thorium slurry concentrations and moderator material (D/sub 2/ O and H/sub 2/O). The prirnary purpose of this study was to determine the influence of thermal stresses on the selection of the core size for the HRE4 reactor. Curves are presented which facilitate relatively rapid determination of stresses for the range of vessels considered. It is concluded that steady- state thermal stresses in the clad or solid stainless steel vessels considered will not have to be a determining factor in the selection of a core size, provided the power density does not exceed approximately 15 kw/l in the clad vessels and 8 kw/l in the solid stainless steel vessels. (auth)
Date: December 31, 1958
Creator: Cheverton, R.D.
Partner: UNT Libraries Government Documents Department

A PRELIMINARY STUDY OF THE NUCLEAR STABILITY OF FLUIDIZED BED REACTORS

Description: A preliminary study was made of the nuclear stability of reactors in which particles containing U/sup 233/ and Th/sup 232/ are fluidized by liquid water. D/sub 2/O moderated reactors were found to be least sensitive to changes in bed height at thorium concentrations in the range 80 to 120 g/liter, H/sub 2/O reactors in the rarnge 1500 io 2400 g Th/ liter, and mixed H/sub 2/O-D/sub 2/O reactors at thorium concentrations between those for pure moderators. A reactor operated at the thorium concentration at which it is least sensitive to change in bed height was found to be stable in response to a cyclical variation in height. (auth)
Date: January 12, 1959
Creator: Benumof, R. & Rosenthal, M.W.
Partner: UNT Libraries Government Documents Department

Spectral Shift Control Reactor Basic Physics Program. Measurement and Analysis of Perturbed Lattices of Slightly Enriched Uo$Sub 2$ Moderated by D$Sub 2$O-H$Sub 2$O Mixtures

Description: Critical experiments and theoretical calculations of reactivity and flux perturbations were performed. Three major critical assemblies were studied; the basic cores had 1.206-cm diameter, aluminum clad, 2.46%-enriched UO/sub 2/ fuel rods on a square lattice pitch of 1.511 cm. Moderator compositions for the three major cores had 0, 50, and 72 mole% D/sub 2/O. Bonic acid was added to keep the core radius constant at 61.11 cm. Data on a zone-loaded core with an inner zone of 93%-enriched aluminum clad UO/sub 2/-ThO/sub 2/ fuel rods surrounded by an outer zone of 4%-enriched stainless steel clad UO/sub 2/ fuel rods are also included. The moderator composition was 81% D/sub 2/O. Perturbers were introduced axially by removing fuel pins to create moderator gaps and by inserting perturbing blades and cruciform rods. The blades were 10 inches wide. The cruciplease delete the above abstract=====
Date: October 1, 1963
Creator: Engelder, T. C.; Clark, R. H.; DeRoche, E. J.; Fairburn, G. T.; Hallam, J. W.; Hostetler, D. R. et al.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT CONCEPTUAL DESIGN STUDY OF CRBR QUICK- OPERATING PRESSURE VESSEL CLOSURE AND SELF-ENERGIZING SEAL TESTS. Final Report

Description: The work to determine the feasibility of using a quickoperating closure for the pressure vessel of the controlled Recirculation Boiling Reactor is described. An outline of the worb performed and the conclusions made is given. Datailed results of the self-energizing seal-evaluation tests are given. (W.D.M.)
Date: October 15, 1950
Creator: Michel, R.G.
Partner: UNT Libraries Government Documents Department

NAVAL REACTORS PHYSICS HANDBOOK. VOLUME I. SELECTED BASIC TECHNIQUES

Description: The purpose of this work is to present the most pertinent parts of the body of physics knowledge which has been built up in the course of the Naval and Shippingport (PWR) Reactor Programs, with the aim of providing a background of understanding for those interested in nuclear core design. Volume 1 of this handbook was planned to bring together topics in the basic theoretical and experimental material which are of especially wide interest, including those common to both thermal and intermediate neutron energy reactor types. The physics design of light water-moderated and -cooled reactors is covered in Volume 2 (classified), and that of intermediate neutron-energy power reactors in Volume 3. The emphasis in Volume 1 is thus on light water reactor systems, and as many recent advances in reactor physics of the Naval and Shippingport Reactor Programs as possible have been included.
Date: January 1, 1964
Creator: Radkowsky, A. ed.
Partner: UNT Libraries Government Documents Department

COST STUDY OF A 100-Mw(e) DIRECT-CYCLE BOILING WATER REACTOR PLANT

Description: A technical and economic evaluation is presented of a direct-cycle light- water boiling reactor designed for natural circulation and internal steam-water separation. The reference lOO-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. (W.D.M.)
Date: July 1, 1960
Creator: Bullinger, C.F. & Harrer, J.M.
Partner: UNT Libraries Government Documents Department

Civilian Power Reactor Program. Part 1. Summary of Technical and Economic Status as of 1959

Description: The current technical and economic status for each reactor concept in the Civilian Power Reactor Program is summarized. The individual techical status reports which present detailed information will be published by AEC as TID-8518. Included in this summary are: power costs for various reactor types versus coal- fired plants; construction schedule for heavy-water natural-U reactors; and annual program costs. (T.R.H.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department

Civilian Power Reactor Program. Part 3. Book 2. Status Report on Pressurized Water Reactors as of 1959

Description: The status of pressurized water reactors on a technical, economic, and operating experience basis is reported. Items covered include concept description, PWR objectives, general research and development prcgram, reactor data, reactor illustrations, operating experience, construction and operation schedules, and present limitations and problems. (W.D.M.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department

A LOW COST PHYSICS AND ENGINEERING TRAINING REACTOR. Reactor Design and Feasibility Study

Description: The conceptual design of a low cost training reactor for the instruction of physicists and engineers is covered. It is conceived as an instructional tool for a course such as that given at the Oak Ridge School of Reactor Technology. The reactor is of a modified pool type, and is designed for a maximum power level of one Mw. This arrangement will accommodate engineering experiments, shielding experiments, and critical experiments as well as being useful as a neutron and gamma source. (auth)
Date: August 1, 1956
Creator: Brown, R.A.; Ackerman, M.W.; Batter, J.F. Jr.; Bell, D.W.; Dunlay, J.B.; Ellis, G.K. et al.
Partner: UNT Libraries Government Documents Department