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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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EPA administrator Lee Zeldin talks the future of nuclear
In a recent interview on New York radio station 77 WABC, administrator of the Environmental Protection Agency Lee Zeldin talked with host John Catsimatidis about the near-term future of the domestic nuclear industry and the role the EPA will play in the sector.
Catsimatidis kicked off the interview by asking if the U.S. will be able to reach total energy independence. Zeldin responded by saying that decreasing energy dependence on other countries, especially adversaries, was a top priority for him and the Trump administration.
Kiyonobu Yamashita, Isao Murata, Ryuichi Shindo
Nuclear Science and Engineering | Volume 110 | Number 2 | February 1992 | Pages 177-185
Technical Notes | doi.org/10.13182/NSE92-A23887
Articles are hosted by Taylor and Francis Online.
The accuracy of the nuclear design code system for the High-Temperature Engineering Test Reactor (HTTR) is evaluated for the neutronic characteristics that depend on core temperature by analyzing the overall temperature coefficients of reactivity and the effective multiplication factors obtained by an experiment in which the Very High Temperature Reactor Critical Assembly (VHTRC) is heated from ambient temperature to 200°C. The core of the VHTRC consists of block-type fuel containing low-enriched uranium (LEU). The nuclear design code system for the HTTR includes the DELIGHT, TWOTRAN-2, and CITATION-1000VP computer codes. The DELIGHT code is a one-dimensional cell burnup code developed to evaluate the nuclear characteristics of HTTR fuel and to calculate the group constants. The calculated overall temperature coefficients of reactivity between ambient temperature and 200°C agree well with the measured coefficients, and the calculated effective multiplication factors for different temperatures agree with measured factors within an uncertainty of 0.6%. From the results, it is concluded that the nuclear design code system for the HTTR predicts well the temperature-dependent neutronic characteristics of a core containing LEU fuel.
