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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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The current status of heat pipe R&D
Idaho National Laboratory under the Department of Energy–sponsored Microreactor Program recently conducted a comprehensive phenomena identification and ranking table (PIRT) exercise aimed at advancing heat pipe technology for microreactor applications.
V. E. Raevskaya
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 393-408
Technical Paper | doi.org/10.13182/NSE86-A18349
Articles are hosted by Taylor and Francis Online.
A method for the calculation of the neutron flux in one-group P3 approximation in a reactor polycell with multizone annular clusters is presented. The cluster central zone contains multizone fuel rods. The rod and cluster neutron fluxes are assumed to be azimuthally symmetrical. Four moments in the scattering function are taken into account. The CLUST code has been developed for computing the neutron fluxes in a reactor polycell. Its numerical results are compared with those of the other codes and appear to be in good agreement with them.
