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
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.
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
Wyoming as a hub for new nuclear manufacturing and microreactor deployment?
A 60-year-old Wyoming industrial machinery company is partnering with nuclear innovator BWX Technologies to deploy 50-megawatt microreactors in America’s heartland over the coming years to provide carbon-free heat and power for industrial users.
Vijay R. Nargundkar, Tejen Kumar Basu, Om Prakash Joneja
Fusion Science and Technology | Volume 12 | Number 3 | November 1987 | Pages 380-394
Technical Paper | Blanket Engineering | doi.org/10.13182/FST87-A25070
Articles are hosted by Taylor and Francis Online.
Neutron multiplication measurements for 14-MeV neutrons were carried out in thick beryllium and graphite assemblies at the Institute for Reactor Development, Jülich, Federal Republic of Germany. Earlier Monte Carlo calculations using the ENDF/B-III library contained systematic errors that did not account for the predominant axial thermalization and non-1/v absorption in polyethylene. In addition, the calculational geometry differed considerably from the experimental geometry. These deficiencies have been eliminated in the present calculations, where the Los Alamos 30-group CLAW-IV library has been used. The anisotropy of the source in space and energy has also been taken into account. The results show that the calculated value of neutron multiplication is 20% higher (originally reported 30% higher) than the measured multiplication in beryllium. The results confirm the measurements made with BeO. For graphite and lead, excellent agreement is found between calculated and measured multiplication.