ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
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!
Latest Magazine Issues
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
World Bank, IAEA partner to fund nuclear energy
The World Bank and the International Atomic Energy Agency signed an agreement last week to cooperate on the construction and financing of advanced nuclear projects in developing countries, marking the first partnership since the bank ended its ban on funding for nuclear energy projects.
Silva Kalcheva, Edgar Koonen, Pol Gubel
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 36-55
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3823
Articles are hosted by Taylor and Francis Online.
The subject of this paper is estimation of the maximum values of the heat flux at steady-state nominal operating conditions in the Belgian Material Test Reactor (BR2) at SCK-CEN in Mol. A strong variation of the fuel depletion and the heat flux with the azimuthal direction and dependence on the orientation of the fuel element in the core are obtained. The full-scale three-dimensional (3-D) MCNP&ORIGEN-S heterogeneous geometry model of BR2 with a detailed 3-D isotopic fuel depletion profile, including a detailed azimuthal fuel modeling in the annular concentric plate fuel elements, is used to evaluate the variation of the heat flux with the azimuthal direction in the hot plane. The relative azimuthal power distribution is calculated with MCNP and introduced into ORIGEN-S to evaluate the azimuthal isotopic fuel profile. The applied detailed azimuthal fuel modeling is compared with homogeneous fuel depletion in the hot plane. An increase of the maximum value of the heat flux of 5% for low burnt fuel and 20% for highly burnt fuel due to the azimuthal modeling of the fuel depletion is obtained. A strong variation of the heat flux with the orientation of the fuel element in the core, modeled with the azimuthal fuel profile, is observed. Perturbation effects in the maximum value of the heat flux of 10% for low burnt fuel and up to 40% for highly burnt fuel, correlated to different orientations of the fuel element in the core, are obtained.