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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
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!
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Latest News
Hinkley Point C gets over $6 billion in financing from Apollo
U.S.-based private capital group Apollo Global has committed £4.5 billion ($6.13 billion) in financing to EDF Energy, primarily to support the U.K.’s Hinkley Point C station. The move addresses funding needs left unmet since China General Nuclear Power Corporation—which originally planned to pay for one-third of the project—exited in 2023 amid U.K. government efforts to reduce Chinese involvement.
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 143-148
Technical Paper | doi.org/10.13182/NSE77-A27017
Articles are hosted by Taylor and Francis Online.
The average 240Pu capture cross section was measured from 200 eV to 350 keV. The cross section was normalized at thermal-neutron energies (0.02 to 0.03 eV), and this normalization was confirmed at the 1.06-eV resonance by the black resonance technique. The source of pulsed neutrons was the Oak Ridge Electron Linear Accelerator. The capture gamma-ray detector used was the “total energy detector,” which is a modification of the Moxon-Rae detector. The shape of the neutron flux was measured relative to the 10B(n, α) cross section up to 2 keV and the 6Li(n, α) cross section at higher neutron energies. The results of the measurement define the average capture cross section of 240Pu over a wide neutron energy range to an accuracy of ∼8%, which is significantly better than previously known. The results indicate that the ENDF/B-IV evaluation is ∼25% low above 30-keV neutron energy. The cross section is important in fast plutonium-fueled reactors.