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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
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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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July 2023
Latest News
The Civil Nuclear Credit Program: An overview
Officially established on November 15, 2021, with the signing of the $1.2 trillion Infrastructure Investment and Jobs Act—aka the Bipartisan Infrastructure Law, or BIL—the Department of Energy’s Civil Nuclear Credit Program was designed to give owners/operators of commercial U.S. reactors the opportunity to apply for certification and competitively bid on credits to help support the continued operation of economically troubled units. Finally, the federal government, and not just certain farsighted state governments, would recognize nuclear energy for its important grid reliability and decarbonization attributes.
Kazuya Takano, Masahiro Fukushima, Taira Hazama, Takayuki Suzuki
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 266-285
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14098
Articles are hosted by Taylor and Francis Online.
The present paper describes the evaluation of the control rod worth data obtained in the Monju restart core. The best-estimate value and its uncertainty are evaluated in detail. As in the criticality evaluation, data obtained in the previous test are evaluated in the same level of detail.Evaluated results of control rod worth are consistent among control rods at symmetrical positions for a random uncertainty. The experimental uncertainty is ±2%, where the dominant uncertainty originates from the delayed neutron parameters used in the period method.The correlation in the uncertainties is also evaluated among different control rods and tests. One can discuss a difference in worth among different control rods and cores without a detailed knowledge of the original uncertainty evaluation.Based on the evaluated data, calculation accuracy is investigated with JENDL-3.3 and JENDL-4.0. It is confirmed that the calculation accuracy is within an experimental uncertainty of ±2% for each layer and 10B content.
