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
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Joint NEA project performs high-burnup test
An article in the OECD Nuclear Energy Agency’s July news bulletin noted that a first test has been completed for the High Burnup Experiments in Reactivity Initiated Accident (HERA) project. The project aim is to understand the performance of light water reactor fuel at high burnup under reactivity-initiated accidents (RIA).
Junhua Luo, Li An, Li Jiang
Nuclear Science and Engineering | Volume 178 | Number 2 | October 2014 | Pages 261-267
Technical Paper | doi.org/10.13182/NSE13-81
Articles are hosted by Taylor and Francis Online.
The cross sections of the 169Tm(n,2n)168Tm reaction induced by neutrons with energies of ∼14 MeV were determined combining the activation technique with the latest decay data. Fast neutrons were produced by using a neutron generator at the China Academy of Engineering Physics, through the 3H(d,n)4He reaction. Induced gamma activities were measured by means of high-resolution gamma-ray spectrometry. Data for 169Tm(n,2n)168Tm reaction cross sections are reported to be 1827 ± 95 and 1926 ± 82 mb at 13.5 ± 0.2 and 14.8 ± 0.2 MeV incident neutron energies, respectively. The cross sections were also estimated with the TALYS-1.4 nuclear model code using different level density models, at neutron energies varying from the reaction threshold to 20 MeV. Results are also discussed and compared with some corresponding values found in the literature.