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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
S. Brandes, H. Daoud, U. Schmid, V. Drüke
Nuclear Science and Engineering | Volume 97 | Number 2 | October 1987 | Pages 89-95
Technical Paper | doi.org/10.13182/NSE87-A27457
Articles are hosted by Taylor and Francis Online.
The pebble-bed prototype thorium high-temperature reactor represents the second step of high-temperature gas-cooled reactor development in the Federal Republic of Germany. Nuclear commissioning of the plant began in August 1983 with the loading of the spherical elements, and first criti-cality was achieved in September 1983 with the loading of 198 180 spherical elements. A very good agreement of 0.004Δk was achieved between measured and calculated values. After full loading of the core with 674200 elements in October 1983, core physics tests were performed in air and nitrogen in August 1984 to verify the design calculations. In these tests the temperature coefficient, the control rod worths, and the reactivity of the reactor core were measured. The measured values of the temperature coefficient were within 10% of the expected values. The agreement between measured and expected control rod worths (5%) is excellent. The reactivity of the cold core with all rods withdrawn was determined to be 0.112 ± 0.005Δp. Taking into account values of the packing density of the spherical elements, which were higher than expected, the calculated value of 0.11Δp was in very good agreement.