ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
May 2024
Fusion Science and Technology
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.
F. G. Bischoff, M. L. Yeater, W. E. Moore
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 266-280
Technical Paper | doi.org/10.13182/NSE48-266
Articles are hosted by Taylor and Francis Online.
A Monte Carlo computer code, MSC, has been developed which is of general usefulness in analyzing double-differential neutron scattering measurements. This code is equivalent to a three-dimensional solution of the neutron transport equation for finite geometries. It is available for two geometrical configurations (slab geometry and tubular geometry), and is readily adapted to other geometrical configurations. Resolution effects are calculated in detail by including full time dependence in the calculation and considering individually the various factors which contribute to the experimental resolution. MSC uses statistical weights as a means to improve the convergence of the Monte Carlo method by forcing scattering collisions; the statistical estimation technique used allows every collision to contribute to every scattered energy and angular bin. Options have been developed which treat rigorously the coherent and incoherent elastic scattering from polycrystals. Scattered energy and angle are sampled at each Monte Carlo collision by means of a new method which samples alpha and beta from the scattering law. This sampling technique is exact within the framework of numerical integration and interpolation. It permits full kernel calculations, yet requires the storage of only two-dimensional arrays. The use of this code led to changes in procedure in the double-differential neutron scattering cross-section experiments at Rensselaer. Because calculated experimental corrections are strongly model dependent, the data have not been corrected for resolution and multiple scattering effects. Instead, resolution-broadened multiple-scattered theory is compared with uncorrected data. This avoids the pitfall of data “corrections” which may, in fact, be strongly model dependent and bias the final results according to the model assumed for the calculation of the correction. This use of uncorrected data enhances the practical value of the measurements as a model testing device. Use of MSC has made it possible to obtain good scattering results with relatively thick samples for several materials, notably water, polyethylene, and uranium carbide. Some examples are given of the verification of the methods used. Experience gained by the use of MSC is summarized.