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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
ANS, UCOR sign MOU for workforce development program
The American Nuclear Society and United Cleanup Oak Ridge have signed a memorandum of understanding that establishes a framework for collaboration to advance ANS workforce training and certification programs serving the nuclear industry.
According to the document, UCOR will provide “operational insights and subject matter expertise to inform ANS’s professional development and credentialing offerings, including the Certified Nuclear Professional [CNP] program.” The collaboration will strengthen UCOR’s workforce development efforts while advancing ANS’s mission to sustain and expand the national nuclear workforce pipeline and capabilities.
Joseph A. Angelo, Jr., Roy G. Post
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 323-330
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31494
Articles are hosted by Taylor and Francis Online.
The heat generated by spent fuel elements and typical processing waste from both a 1000 MW(e) reference design pressurized water reactor (PWR) and 1160 MW(e) reference design high temperature gas-cooled reactor (HTGR) were calculated for times up to 1000 years. To compensate for differences in exposure, the heat generated was expressed in terms of watts of heat generated per megawatt day of exposure. Examination of both tabular data and graphical presentations of these normalized heat generation data indicates noticeable differences in the contribution of different isotopes for each system. As anticipated, the heat generation for each fuel was greatly influenced by the transmuted isotopes 233Pa and 238Pu for the HTGR with 137Cs and 90Sr for the PWR. Data provide quantitative detailed information on the thermal power output of typical processing waste for both reactor systems for the first millennium of cooling.