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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Science and Engineering
August 2025
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July 2025
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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.
H. H. Wang
Nuclear Science and Engineering | Volume 67 | Number 2 | August 1978 | Pages 162-171
Technical Paper | doi.org/10.13182/NSE78-A15433
Articles are hosted by Taylor and Francis Online.
The symmetric successive overrelaxation (SSOR) method and the symmetric strongly implicit procedure (SSIP) method are applied to a number of two-dimensional elliptic partial differential equations typical of those encountered in reactor engineering. The SSIP method is then incorporated in a program for multigroup diffusion calculation to compute the inner iterations. The results of applying the program to the solution of several reactor configurations are compared with the results from a version of the PDQ code. For cell problems (with Neumann boundary condition), the new methods outperform the SOR method.
