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DESIGN AND HAZARDS REPORT FOR THE ARGONNE FAST SOURCE REACTOR (AFSR)

Description: The Argonne Fast Source Reactor is designed to operate at low power (nominally 1000 watts) to supply neutron fluxes, both fast and thermal, for laboratory experiments. It is built around a cylindrical core (with vertical axis) of solid, highly enriched uranium approximately 4 1/2 in. in diam. by 4/4 in. high. The blanket is of solid depleted uranium with a minimum thickness of eight in.; its outer form is cylindrical, 20 5/8 in. in diam. by 20 5/8 in. high. The reactor, contained in a shield of high density concrete of minimum thickness 4 1/2 ft, is freestanding on the floor of the reactor building. A graphite thermal column 4 x 4 x 6 ft is provided. All control and safety mechanisms are located in a pit beneath the reactor. The hazards associated with operation of the reactor have been analyzed. A number of potentially dangerous circumstances were studied to determine the probable severity of the resultant excursions. As an upper limit, a detailed study was made of the extreme case in which the reactor, overloaded by five kilograms of U/sup 235/, goes critical at the air cylinder speed of 18 in./min. It is estimated that the excursion would amount to 3.6 x 10/sup 17/ fissions. This is expected to destroy the core and eject all core material into the pit where it burns, greatly adding to the total energy of the excursion. No rupture of reactor shield or building is expected. The reactor pit and reactor building will be heavily contaminated and some radioactive material will escape from the building. It is nearly certain that the maximum radiation dose to personnel outside the reactor building will not exceed 15 roentgens. (auth)
Date: June 1, 1959
Creator: Brunson, G.S.
Partner: UNT Libraries Government Documents Department

BORAX V EXPONENTIAL EXPERIMENT

Description: The cadmium ratio was measured in an exponential mockup of Borax V as a function of the void fraction. The extent of voids, simulated by lengths of closed polyethylene tubes, ranged from 0 to 40%. The corresponding cadmium ratios ranged from 6.1 to 4.6. The exponential was also used to determine the radial flux pattern across a Borax-type fuel assembly and the fine flux detail in and around fuel rods. For a normal loading the maximum-to-average power generation across an assembly was 1.24. (auth)
Date: April 1, 1963
Creator: Kirn, F.S. & Hagen, J.I.
Partner: UNT Libraries Government Documents Department

A COMPARISON OF EXPERIMENTAL AND CALCULATED PROMPT NEUTRON LIFE-TIMES AND CENTRAL REACTIVITY COEFFICIENTS IN ZPR-III ASSEMBLIES AND THEIR RELATIONSHIP TO OTHER REACTOR PARAMETERS

Description: Experimental parameters of ZPR-HI fast reactor assemblies were compared with those calculated through use of a cross-section set derived from that of Yiftah, Okrent, and Moldauer, and initially used for a study of the critical sizes of ZPR-III assemblies. This cross-section set waa also used to study central fission ratios in ZPR-III assemblies. The analysis was extended to prompt neutron lifetimes and the relative reactivity effects of the substitution of materials at the reactor centers. The results of the work were examined in conjunction with those of the critical size and fission ratio studies. (auth)
Date: June 1, 1963
Creator: Davey, W.G.
Partner: UNT Libraries Government Documents Department

TWO SPHERICAL FAST CRITICAL EXPERIMENTS (ZPR-III ASSEMBLIES 38 AND 39)

Description: Two spherical versions of earlier cylindrical assemblies were used for a critical study of shape effects for fast reactor cores with volumes of 300 to 400 liters. Assemblies 24 (cylindrical) and 38 (spherical) had a high-density metallic U blanket, whereas the set of assemblies numbered 31 (cylindrical) and 39 (spherical) had a low-density U-fueled core (with steel and Al diluents) with a highdensity blanket of depleted U. The main features of these assemblies are summarized. Reactivity coefficients of a small number of fissile and nonfissile materials were measured in both assemblies (38 and 39). In Assembly 38 the effects of environment, etc., upon fission rates measured with absolute fission chambers were investigated. Radial fission rate traverses in different directions were made in Assembly 39 to reveal any flux asymmetry due to heterogeneity of the core; no such effect was detected.(auth)
Date: July 1, 1962
Creator: Bates, J.C.; Davey, W.G.; Amundson, P.I.; Gasidlo, J.M.; Long, J.K. & Keeney, W.P.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF CORE B FOR THE ENRICO FERMI ATOMIC POWER PLANT (ZPR-III ASSEMBLY NO. 35)

Description: Critical studies of a simplified mockup of the second loading (Core B) for the Enrico Fermi fast reactor were made. The core consists of a fully enriched, UO/sub 2/-stainless steel cermet clad in stainless steel and cooled by sodium. The high critical mass found for the reactor mockup led to a series of experiments on reducing neutron leakage from the core by surrounding it with different reflectors. With a nickel reflector in place, measurements were made of the reactivity worths of various engineering features of the Fermi reactor, distributed and local reactivity coefficients, various fission and capture rates and fission ratios, and the prompt-neutron lifetime. Finally, with a nickel oxide reflector in place, some of the above measurements were repeated. (auth)
Date: February 1, 1963
Creator: Doyle, T.A. & Hess, A.L.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF URANIUM-STEEL AND URANIUM-STEEL-SODIUM FAST REACTOR CORES. (ZPR-III ASSEMBLIES 32 and 33

Description: S>Critical studies of two fast reactor cores are described: one contains uranium and steel; the other contains uranium, steel, and sodium. Experimental results are given for fission ratio, central and edge reactivity coefficients, fuel bunching, average prompt neutron lifetime, and distributed worth measurements. (auth)
Date: February 1, 1963
Creator: Amundson, P.I.; Gemmell, W.; Long, J.K. & McVean, R.L.
Partner: UNT Libraries Government Documents Department

A SUBCRITICAL PLUTONIUM-FUELED FAST REACTOR CORE (ZPR-III ASSEMBLY 37)

Description: A subcritical fast reactor, fueled with Pu, is described. Calculations and experimental measurements of neutron flux and gamma dose rates near the bare core face are reported, as well as the core temperature increase eaused by Pu alpha and gamma heating. (auth)
Date: July 1, 1962
Creator: Amundson, P.I.; Jiacoretti, R.; Long, J.K. & McVean, R.L.
Partner: UNT Libraries Government Documents Department

CRITICAL STUDIES OF A SMALL URANIUM CARBIDE-FUELED REACTOR WITH A BERYLLIUM REFLECTOR. (ZPR-III ASSEMBLY 40)

Description: A small, lightweight, uranium carbide-fueled reactor with a beryllium reflector surrounding the core was mocked up as Assembly 40. It was determined that the presence of beryllium in the axial and radial reflectors did not endanger the safe loading and operation of the' critical assembly. The actual experiment consisted of determination of the critical mass, measurement of the reactivity coefficients for a large number of fissile and nonfissile materials, the performance of radial and axial fission traverses, and measurement of central fission ratios. The effectiveness of the radial beryllium reflectcr as a control mechanism was determined and the Rossialpha was measured. (auth)
Date: April 1, 1963
Creator: McVean, R.L.; Amundson, P.I.; Brunson, G.S. & Gasidlo, J.M.
Partner: UNT Libraries Government Documents Department