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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.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.