Showing papers in "Nuclear Technology in 1973"
TL;DR: An accurate prediction of the hydraulic losses in multi-rod fuel bundles is necessary for reactor design calculations as discussed by the authors, and the relationship of the pressure drop at the spacers is important for these calcul...
Abstract: An accurate prediction of the hydraulic losses in multirod fuel bundles is necessary for reactor design calculations. Correlations of the pressure drop at the spacers are important for these calcul...
278 citations
TL;DR: In this paper, high energy electromagnetic processes in Condensed Media have been studied in the context of high energy electromagnetic processes in the nuclear power plant. But they are not considered in this paper.
Abstract: (1973). High-Energy Electromagnetic Processes in Condensed Media. Nuclear Technology: Vol. 18, No. 3, pp. 312-313.
277 citations
TL;DR: In this paper, the quantum theory on nonrelativistic collisions has been studied in the context of nuclear technology. But this paper is not related to the present paper, as discussed earlier.
Abstract: (1973). Scattering Theory: The Quantum Theory on Nonrelativistic Collisions. Nuclear Technology: Vol. 18, No. 3, pp. 313-313.
77 citations
TL;DR: The 14-MeV neutrons from a controlled DT fusion plasma can potentially be used to produce neutron source multiplication and energy multiplication through fission in a heavy-element blanket surround.
Abstract: The 14-MeV neutrons from a controlled DT fusion plasma can potentially be used to produce neutron source multiplication and energy multiplication through fission in a heavy-element blanket surround...
74 citations
TL;DR: In this paper, a new contactor was developed for solvent extraction processing of high-plutonium-content fuels, which has a vertically suspended rotor that has a 4-in. inside diameter.
Abstract: A centrifugal contactor of unique design has been developed for solvent extraction processing of high-plutonium-content fuels. The unit has a vertically suspended rotor that has a 4-in. inside diam...
64 citations
Journal Article•
45 citations
TL;DR: The shuffling logic employed in SHUFLE was demonstrated adequate to predict acceptable loading patterns for initial, equilibrium, and nonequilibrium pressurized water reactor cores.
Abstract: An iterative approach was adopted as the most practical method to search for an optimum fuel loading pattern in pressurized water reactors. A minimum peak-to-average power ratio was chosen as the o...
37 citations
TL;DR: In this article, an equilibration method was developed to measure accurately the activity of carbon in liquid sodium, and an equilibrium method was used to measure carbon activity in liquid carbon dioxide.
Abstract: An equilibration method has been developed to measure accurately the activity of carbon in liquid sodium. Foils of Fe – 8 wt% Ni, Fe – 16 wt% Ni, and Fe – 18 wt% Cr – 8 wt% Ni alloys can be exposed...
34 citations
27 citations
TL;DR: In this article, four different methods for the conversion of UF6 to ceramic grade UO2 powder have been developed to an industrial scale and two of them, the ADU and AUC processes, are based upon precipitation of uran...
Abstract: Four different methods for the conversion of UF6 to ceramic grade UO2 powder have been developed to an industrial scale. Two of them, the ADU and AUC processes, are based upon precipitation of uran...
26 citations
TL;DR: An ultrasonic technique was used to determine elastic moduli of Type-304 stainless-steel samples irradiated to fluences as high as 7.5 × 1022 n/cm2 (E > 0.1 MeV) as mentioned in this paper.
Abstract: An ultrasonic technique was used to determine elastic moduli of Type-304 stainless-steel samples irradiated to fluences as high as 7.5 × 1022 n/cm2 (E > 0.1 MeV). Significant decreases in the elast...
TL;DR: The results of a series of irradiations of refractory fuels at cladding surface temperatures from 1000 to 1900°C were examined to determine which factors have the greatest influence on swelling rat as discussed by the authors.
Abstract: The results of a series of irradiations of refractory fuels at cladding surface temperatures from 1000 to 1900°C were examined to determine which factors have the greatest influence on swelling rat...
TL;DR: In this paper, the authors compared track-etch with conventional film-detection methods in terms of exposure requirements, spatial resolution, contrast, and convenience, and showed that tracketch techniques can give comparable or better results.
Abstract: Several polycarbonate plastics and cellulose nitrate have been studied for radiographic imaging studies with alpha particles, protons, fast neutrons, and thermal neutrons. Comparisons, made with conventional film-detection methods in terms of exposure requirements, spatial resolution, contrast, and convenience, show that track-etch techniques can give comparable or better results. Comprehensive results for thermal-neutron radiography indicate that total thermal-neutron exposures in the range of 2 × 107 to 4 × 108 n/cm2 provide radiographs which display a contrast sensitivity of 1 to 3% and a spatial resolution of ∼25 μm. A scattered-light enlargement technique provides a simple means to improve visual contrast of track-etch images.
TL;DR: In this paper, the linear thermal expansion of stoichiometric 239PuO2 was measured from 25 to 1420°C and a polynomial least-squares fit of the expansion data yielded the linear expansion expression [in cm/ (cm °C)]:
Abstract: The linear thermal expansion of stoichiometric 239PuO2 was measured from 25 to 1420°C. A polynomial least-squares fit of the expansion data yielded the linear expansion expression [in cm/ (cm °C)]:The mean linear expansion coefficient from 25 to 1420° C was 11.16 × 10−6 cm/(cm °C).
TL;DR: In this article, the authors apply the hypothetical accident approach to analysis of fast reactors and apply it to the meltdown of an entire core and its interaction with containment floor materials of construction.
Abstract: The hypothetical accident approach to analysis of fast reactors has been applied to the meltdown of an entire core and its interaction with containment floor materials of construction. The objectiv...
TL;DR: In this paper, an out-of-reactor simulator was developed that simulates both in-Reactor thermal gradients and heating rates in oxide fuel pellet stacks through direct electrical heating, and preliminary results of tests of both steady-state and transient operation indicate that fuel phenomena and fuel microstructures similar to those observed in actual inreactor transients can be produced.
Abstract: An apparatus has been developed that simulates, out-of-reactor, both in- reactor thermal gradients and heating rates in oxide fuel pellet stacks through direct electrical heating. Preliminary results of tests of both steady-state and transient operation indicate that fuel phenomena and fuel microstructures similar to those observed in actual in-reactor transients can be produced. (6 references) (auth)
TL;DR: The postirradiation fatigue-crack propagation behavior of solution-annealed Type-304 and 20% cold-worked Type-316 stainless steels irradiated to a fluence of 1.3 × 1021 n/cm2 (E > 0.1 MeV) at temper...
Abstract: The postirradiation fatigue-crack propagation behavior of solution-annealed Type-304 and 20% cold-worked Type-316 stainless steels irradiated to a fluence of 1.3 × 1021 n/cm2 (E >0.1 MeV) at temper...
TL;DR: In this paper, the performance of Zircaloy-clad thermal reactor mixed-oxide fuels was evaluated under a wide range of test conditions, including peak linear heat ratings sufficient to cause fuel melting and peak burnups to over 50 000 MWd/MTM.
Abstract: Irradiation performance data available to date indicate that the behavior of Zircaloy-clad thermal reactor mixed-oxide fuels is entirely satisfactory. There do not appear to be any inherent performance limitations created by the addition of small amounts of PuO2 to UO2. The wide range of test conditions include peak linear heat ratings sufficient to cause fuel melting and peak burnups to over 50 000 MWd/MTM.Because small PuO2 additions to UO2 have an insignificant effect on those fuel properties which could affect irradiation behavior, thermal reactor mixed-oxide fuel performs similarly and equally as well as UO2-only fuel. The evidence indicates that the PuO2-rich regions that persist in nonrestructured mechanically mixed, mixed-oxide fuel have an insignificant effect on performance. The extent of plutonium migration which can occur during irradiation also has an insignificant effect on mixed-oxide fuel behavior. Satisfactory defect behavior of Zircaloy-clad UO2-PuO2 fuel under normal operating condition...
TL;DR: (1973).
Abstract: (1973) Microscopic Theory of the Nucleus Nuclear Technology: Vol 18, No 3, pp 313-314
TL;DR: In this article, a generalized plutonium value equation is given which permits corrections for changes in separative work and uranium price:Pu value = AU - 0.16P(incremental fabrication cost per kg fuel/g of fissil...
Abstract: A generalized plutonium value equation is given which permits corrections for changes in separative work and uranium price:Pu value = AU - 0.16P(incremental fabrication cost per kg fuel/g of fissil...
TL;DR: In this paper, the neutron yield from a small high purity 238PuO2 source has been measured to be 1.705 × 104 n/sec per gram with an accuracy of better than 1%.
Abstract: The neutron yield from a small high purity 238PuO2 source has been measured to be 1.705 × 104 n/sec per gram of 238Pu with an accuracy of better than 1%.
TL;DR: In this article, the effects of variations in plutonium isotopic composition, due to differences in reactor types and fuel exposure, and the resultant combined effects on personnel radiation exposure are described, and it is concluded that increased shielding will be required for plutonium fuel fabrication facilities when full-scale plutonium recycle is under way.
Abstract: Personnel radiation exposure problems in fabricating and handling plutonium fuels are described. The effects of variations in plutonium isotopic composition, due to differences in reactor types and fuel exposure and the resultant combined effects on personnel radiation exposure, are also described. It is concluded that increased shielding will be required for plutonium fuel fabrication facilities when full-scale plutonium recycle is under way, due to the higher radiation levels associated with high exposure plutonium and to more restrictive personnel radiation exposure limits than those currently used. However, it should be possible to handle completed plutonium fuel assemblies containing high exposure plutonium without excessive personnel exposure and with a minimum of special handling procedures.
TL;DR: The vanadium-wire equilibration method was used in this article to determine the three-phase equilibrium of Na/sub 2/O with mixed-oxide fuel at temperatures of 650 to 900 deg C for fuels with oxygen to metal ratios of 1.90, 1.94, and 1.97.
Abstract: The oxygen concentration of sodium in equilibrium with uranium-25% plutonium oxide fuel was measured at temperatures of 650 to 900 deg C for fuels with oxygen-to-metal ratios of 1.90, 1.94, and 1.97. The oxygen concentration in sodium at the three-phase Na -- MO/sub 2-x/ Na/sub 3/MO/sub 4/ (M = uranium plus plutonium) equilibrium has also been measured for the same temperature range. This three-phase equilibrium was established by reacting mixed-oxide fuel with sodium to which Na/sub 2/O had been added. The oxygen concentrations in sodium were determined by the vanadium-wire equilibration method. The oxygen concentration in sodium at the three-phase equilibrium varied from ~ 0.1 to 0.4 ppM in the temperature range investigated. Oxygen concentrations in EBR-II primary sodium, which have been measured by the same method, vary from 0.4 to 0.9 ppM oxygen depending on the cold-trap operation. These values indicate that the sodium--fuel reaction product, i.e., Na/sub 3/MO/sub 4/, is stable in sodium at the temperatures (<1000 deg C) and oxygen levels present in EBR-II. (auth)