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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Mark L. Williams, R. Q. Wright, Brian A. Worley, Odelli Ozer, Walter J. Eich
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 386-401
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33691
Articles are hosted by Taylor and Francis Online.
Thermal reactor benchmark calculations have been performed with the “design codes” EPRI-CELL and PDQ using ENDF/B-V cross-section data. The purpose of these calculations is to determine the quality of ENDF/B-V data for predicting reactor parameters when used with methods typically employed for power reactor analysis. This verification is essential if ENDF/B-V cross sections are to be used widely by the nuclear industry for reactor design, core reload, and core-follow studies. It appears that ENDF/B-V, when used in typical reactor design codes, is an accurate data set for light water reactor analysis. Computed resonance integrals and reaction ratios for 238U seem to be slightly high but are within the uncertainty. The average keff obtained for a diverse set of 27 UO2 and MO2 critical configurations is 1.002 ± 0.002. Critical UO2 eigenvalues are consistently slightly overestimated, on the average by 0.2%. The average eigenvalue obtained for the mixed-oxide lattices is 1.0007 with a standard deviation of 0.0023. Plutonium isotopic ratios generally show good agreement with measured values obtained from burned power reactor pins.