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
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
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
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
W. J. M. de Kruijf, A. J. Janssen
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 121-135
Technical Paper | doi.org/10.13182/NSE94-108
Articles are hosted by Taylor and Francis Online.
Calculations of resonance absorption for simple temperature profiles both in a slab and in a pin of 238UO2 are presented to show the influence of a nonuniform fuel temperature profile on the choice of the equivalent uniform temperature, or the effective fuel temperature. The effective fuel temperature is given as a weighted average of the temperatures in the fuel zones. Two simple theoretical expressions for this weighted average, derived from the literature, are discussed. First, for high absorption, the effective fuel temperature is given by the so-called chord-averaged fuel temperature. Second, for low absorption, the effective fuel temperature is given by the volume-averaged fuel temperature. The results for a slab of 238UO2 show that a bruteforce method is necessary to calculate an accurate effective fuel temperature. A set of weights for one specific 238UO2 pin is calculated. This set agrees well with the chord-averaged fuel temperature. However, this appears to be a coincidence because the results for specific neutron energy ranges do not agree with this set of weights.