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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
L. W. Nordheim
Nuclear Science and Engineering | Volume 12 | Number 4 | April 1962 | Pages 457-463
Technical Paper | doi.org/10.13182/NSE62-A26091
Articles are hosted by Taylor and Francis Online.
A new method for the calculation of resonance integrals for both homogeneous and heterogeneous assemblies has been developed and programmed for the IBM-7090. It consists in a direct numerical solution of the integral equation for the average flux in the absorber, and obviates the necessity of choosing between the narrow and wide resonance approximations. Cross sections are calculated, inclusive of Doppler broadening, interference scattering, and the E−1/2 factor in the absorption cross section. The unresolved resonances are calculated in the narrow resonance approximation under consideration of the Porter-Thomas distribution of neutron widths. Available options include (1) choice of geometry—spherical, cylindrical, slab, and homogeneous; (2) Dancoff correction for absorbers of arbitrary transparency; and (3) integral treatment of admixed scatterers. The only input data required are the resonance parameters and specifications of temperature, composition, and geometry. Everything else is handled automatically. The program calculates directly the cases of interest without requiring any additional data handling. Resonance integrals have been computed for uranium and thorium metal and UO2 and ThO2 rods of various diameters and different temperatures. Quantitative agreement with the best available measurements is reached for U238, with respect to the absolute values of the resonance integrals, as well as with respect to their temperature dependence. An interesting new result is that the intergral treatment of the oxygen in UO2 gives a noticeable correction to the resonance integral for thick absorber rods. For Th232, the agreement is not quite as perfect. The differences can, however, be traced to inconsistencies in the available cross section data.