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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Hiroshi Takahashi
Fusion Science and Technology | Volume 5 | Number 1 | January 1984 | Pages 72-79
Deep Penetration: Problem and Method of Solution | Special Section Contents / Shielding | doi.org/10.13182/FST84-A23080
Articles are hosted by Taylor and Francis Online.
The integral transport method, which has been used in the early calculation of a beam hole tube in an experimental reactor and many reactor parameters of a power reactor; has been reviewed. The Generalized First-Flight Collision Probability (GFFCP) method, based on the integral transport equation, and the discrete ordinates method, based on the differential transport equation, are compared in the context of the deep penetration problem. The direct integral method derived from the partial integral transport equation, which eliminates many of the drawbacks of the GFFCP method, is discussed. A method similar to the GFFCP method, which needs spherical harmonics expansion instead of the discrete ordinates scheme, is presented. The future of these analytical methods is discussed in the comparison with the straight numerical method based on the differential transport calculation and the Monte Carlo calculation.