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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Latest News
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
S. I. Bhuiyan, Anisur Rashid Khan, M. M. Sarker, M. Rahman, Z. Gulshan Ara, M. Musa, M. A. Mannan, I. Mele
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 253-263
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34633
Articles are hosted by Taylor and Francis Online.
A data base for the TRIGAP code is generated for the 3-MW TRIGA MARK-II research reactor in Bangladesh. The library is created using the WIMS-D/4 code. Cross sections are calculated from zero burnup to 37% of initial 235U in 20 burnup steps. The created TRIGAP library is tested through practical calculations and is compared with experimental values or with values in the safety analysis report (SAR). Excess reactivity of the fresh core configuration is measured and determined to be 10.27 $, while a value of 10.267 $ is obtained using the generated library. By choosing burnup steps of 0, 50, 350, and 750 MW.h, the whole operating history is covered. The calculated temperature defect at 1 and 3 MW is 1.15 and 3.59 $ compared with the experimental values of 1.02 and 3.64 $, respectively. The xenon value obtained at 1 and 3 MW is 2.21 and 3.20 $, respectively, compared with 3.57 $ at 3 MW in the SAR. The TRIGAP code with its new library is used for calculating fast and thermal flux distributions close to values from the SAR. The temperature coefficient of low-enrichment uranium fuel, calculated for three different burnups, shows a good agreement with the SAR. The TRIGAP and WIMS-D/4 codes are applied to power-peaking calculations. Total peaking factors calculated as products of axial, radial, and hot rod peaking factors for four configurations are (a) the compact core with graphite reflector, 3.15; (b) the same core with water reflector, 3.39; (c) the core with a central thimble, graphite reflector, 5.01; and (d) the same core with a water reflector, 5.29. In the SAR, the total peaking factor for the compact core is 3.5 and with a central thimble, 5.63. Excellent agreement between calculations and measurements establishes the validity of the library.