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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
P. K. Job, M. Srinivasan, V. R. Nargundkar
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 87-96
Technical Note | Reactor | doi.org/10.13182/NT80-A32560
Articles are hosted by Taylor and Francis Online.
A series of subcritical multiplication experiments was conducted at Purnima Laboratories, Trombay, on a thick BeO-reflected 233U (98.2 wt% enrichment) uranyl nitrate solution system. The core tank was a rectangular parallelepiped of 0.11− × 0.11−m2 sectional area attached to the bottom of a glove box. Multiplication measurements were carried out with uranyl nitrate solutions in the uranium concentration range of 25 to 150 kg/m3 corresponding to H/233U ratios in the range of 1200 to 200. The maximum quantity of 233U-enriched uranium used was 0.12 kg and the corresponding multiplication was ∼5. Boric acid solutions, equivalent in terms of thermal-neutron absorption to the uranium solutions, were used to eliminate the unmultiplied neutron background and to calibrate the neutron detection system. Extrapolated critical heights determined from plots of inverse multiplication were used to obtain the keff of the subcritical assembly with the help of the Trombay Criticality Formula. Absolute multiplication and keff were also deduced independently from the observed multiplication data relative to a reference dummy core. The experimental keff results are found to be in good agreement with detailed transport theory and Monte Carlo calculations.