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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

HIGH FLUX RESEARCH REACTOR (HFRR). Reactor Design and Feasibility Study

Description: Feasibility studies of a high flux, solid fuel research reactor are presented. By means of a parameter study, a reactor consisting of a cylindricai fuel annulus submerged in heavy water is described. The thermal neutron flux peaks in the heavy water adjacent to the annulus and is a maximum in the region surrounded by the fuel annulus.. while the minimum thermal flux occurs in the annulus. The fast flux has the opposite shape. Calculations indicate that practical peaking factors, ratios of maximum thermal flux in the heavy water to average thermal flux in the fuel annulus, as high as eight can be obtained. A typical reactor in which the maximum thermal and fast fluxes are greater than 10/ sup 15/n/cm/sup 2/-sec is also described. (auth)
Date: August 1, 1956
Creator: Cheverton, R.D.f Charmatz, A.W.f Crowther, R.L.f Feinberg, R.J.; Maortensen, G.A. & Schleiter, T.G.
Partner: UNT Libraries Government Documents Department

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

CIVILIAN POWER REACTOR PROGRAM. PART II. ECONOMIC POTENTIAL AND DEVELOPMENT PROGRAM. HEAVY WATER-MODERATED POWER REACTOR

Description: The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel development program, and improvements which would result from the successful completion of the development program as presented. One plant size was used in the evaluation of plant potential, with a 300 Mw/sub e/ nominal rating. The boiling D/sub 2/O-cooled, pressure tube direct cycle plant design was used. The current development program is outlined; this work includes several items leading to the long-range development of the concept. (auth)
Date: August 19, 1960
Creator: Hutton, J.H.; Davis, S.A.; Graves, C.C. & Duffy, J.G. comps.
Partner: UNT Libraries Government Documents Department

Determination of Heavy Water Purity by Infrared Absorption

Description: The practical application of heavy water purity determination by infrared absorption spectroscopy using standard laboratory equipment was demonstrated in connection with the operation of heavy water-moderated Special Power Excursion Reactor Test (SPERT II) Facillty at the NRTS. (auth)
Date: January 16, 1962
Creator: Abernathey, R. M. & Morgan, T. D.
Partner: UNT Libraries Government Documents Department

HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR NOVEMBER 1959

Description: At the end of November, 20% of the construction and 80% of the firm design of the Heavy Water Components Test Reactor (HWCTR) were complete. Proof testing of various seals and mechanisms for the HWCTR continued satisfatorily. Further analyses are given of the transient behavior of the HWCTR isolated coolant loops and of the experimental data on the nuclear effects of hot moderator. The results of additional fabrication and irradiation tests of uranium metal and uranium oxide are recorded. The manufacture of tubular metallurgical joints between Zircaloy and stainless steel is also reported. (See also DP-415.) (auth)
Date: December 1, 1959
Creator: Hood, R.R. & Isakoff, L. comps.
Partner: UNT Libraries Government Documents Department

HEAVY-WATER-MODERATED POWER REACTORS ENGINEERING AND ECONOMIC EVALUATIONS. VOLUME I. SUMMARY REPORT

Description: Capital investments and the cost of power were estimated for 21 heavy- water-moderated, natural-uraniumfueled power-reactor plants, ranging in capacity from 100 to 460 Mw(e). Comparisons were made of hot- and coldmoderator reactors and of the relative merits of pressuretube and pressure-vessel designs. Reactors cooled with liquid D/sub 2/O, boiling D/sub 2/O, /sub 2/O steam, and helium were evalunted. A cold-moderator pressure-tube reactor cooled with boiling D/sub 2/O shows the most economic promise of the D/sub 2/Omoderated reactor systems studied to date. Reactors of this type have sufficient reactivity to permit satisfactory fuel exposures, but the development of additional technology is a prerequisite for optimum designs. At capacities of 300 and 400 Mw(e), the estimated power costs from the current designs of boiling-D/sub 2/O pressure-tabe reactor plants are 11.3 and 9.8 mills/kwh, respectively. From liquid-D/sub 2/-cooled concepts of comparable capacities the indicated power costs are 7 to 20% higher. With an active development program, a power cost of 8.0 to 8.5 mills/kwh may be attained in a 300 Mw(e) boiling-D/sub 2/O reactor plant within the next decade. (auth)
Date: June 1, 1960
Partner: UNT Libraries Government Documents Department

HEAVY-WATER-MODERATED POWER REACTORS ENGINEERING AND ECONOMIC EVALUATIONS. VOLUME II. ENGINEERING STUDIES AND TECHNICAL DATA

Description: The results of preliminary design and evaluation studies of various concepts of a power reactor that is moderated by heavy water and fueled with natural uranium are presented. Twenty-nine conceptal designs were developed for reactors ranging in capacity from 100 Mwe to 460 Mwe. Resigns were prepared for hot- and cold-moderator reac tors of the pressure vessel type, with liquid D/sub 2/O, boiling D/sub 2/O, E/sub 2/O steam, and helium as coolants. Also studied were cold-moderator pressure tube reactors cooled with liquid D/sub 2/O and boiling D/sub 2/O. The repont includes the results of engineering studies of the reactor systems, electrical generation facilities, and auxiliary equipment. (auth)
Date: December 1, 1960
Partner: UNT Libraries Government Documents Department

HEAVY WATER MODERATED POWER REACTORS. Progress Report for December 1959

Description: At the end of 1959, 25% of the construction and 85% of the firm design of the Heavy Water Components Test Reactor (HWCTR) were complete. Further safeguards analyses of the HWCTR, done with the aid of analog and digital computers, corroberated earlier data which indicated that the reactor is highly self-regulating, and that the safety system should prevent release of radioactivity outside the containment building. Fabrication tests of metallic uranium fuels and preparation of irradiation specimens of swaged uranium oxide fuel tubes continued. A tube of Zircaloy-2-clad U-2 wt.% Zr failed during a low temperature, low pressure irradiation test to modest exposure. Preliminary examinations of tubular metallurgical joints between Zircaloy and stalnless steel were promising. (For preceding period see DP-445.) (J.R.D.)
Date: January 1, 1960
Creator: Hood, R.R. & Isakoff, L. comps.
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

POWER COST NORMALIZATION STUDIES CIVILIAN POWER REACTOR PROGRAM--Sept. 1, 1959

Description: In connection with the development of a comprehensive plan for a ten- year civilian power reactor program, the AEC has had a series of status reports prepared to present a comprehensive review of the technical and economic status of various nuclear power reactor concepts. In as much as the economic data reported by the various contractors reflected different design philosophies, different estimating policies, and in some cases a technology not verified by the AEC definition of current status, Sargent and Lundy was requested to review the aforementioned status reports and to prepare normalized cost estimates of each of eight reactor concepts. The reactors were studied in three plant sizes: 75, 200, and 300 Mw(e). The reactor concepts considered were pressurized water, boiling water, organic cooled, sodium graphite, liquid metal cooled, fluid fuel (aqueous homogeneous), heavy water moderated, and gas cooled. (W.D.M.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department

Civilian Power Reactor Program. Part 3. Status Report on Gas-Cooled Reactors as of 1959. Book 8

Description: The technology of natural-uranium-fueled graphitemoderated gas-cooled reactor power plants is summarized for its relevance to the technology of enriched-fuel graphite-moderated systems. The technology of D/sub 2/Omoderated gas-cooled reactors is also summarized. Estimated technical performance parameters are given for the enriched-fuel prototype and for a large natural- uraniumfueled plant. Current technical status is discussed in terms of reactor physics, heat transfer and fluid flow, core materials, components, plant design and conctruction, and hazards. Detailed tables of characteristics for various reactors are given. An extensive bibliography is included. (W.D.M.)
Date: January 1, 1960
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