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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Mohammad Abdul Motalab, Woosong Kim, Yonghee Kim
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1185-1204
Technical Paper | doi.org/10.1080/00295450.2019.1582942
Articles are hosted by Taylor and Francis Online.
This paper is concerned with an improved two-step methodology based on the nodal equivalence theory for more accurate and consistent CANDU reactor analysis. In addition, the albedo-corrected parameterized equivalence constants (APEC) method is introduced to achieve further improvement of the nodal solution by correcting the burnup-dependent cross sections (XSs) and discontinuity factors (DFs). The APEC algorithm is incorporated into an in-house nodal expansion method (NEM) code. Colorset calculations are performed to obtain physically meaningful leakage information of the fuel lattice, and the results are used for generating burnup-dependent APEC functions to correct groupwise XSs and DFs. The NEM-equivalent reference DF on each surface of the colorset are calculated for a coarse mesh (1 × 1 mesh per fuel assembly) using the net-current boundary conditions. These reference DFs are used to determine the DF APEC functions. A separate set of burnup-dependent APEC functions is generated for the fuel lattice loaded with a reactivity device. Both position- and burnup-dependent APEC functions are applied for accurate CANDU core analysis. A two-dimensional CANDU whole-core nodal analysis is performed to show the effectiveness of the APEC corrections. Moreover, several variants of the original benchmark are also analyzed with the same APEC functions to confirm the general applicability of the predetermined APEC functions. In addition, NEM calculations are performed for a CANDU core with a reactivity device and its variants with different burnup profiles. Numerical results show that the APEC-based two-step nodal methodology can provide an accurate and consistent solution for burned CANDU cores with reactivity device.