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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.
Richard W. Benjamin, John A. Harvey, Nathaniel W. Hill, Madhu S. Pandey, Robert F. Carlton
Nuclear Science and Engineering | Volume 85 | Number 3 | November 1983 | Pages 261-270
Technical Paper | doi.org/10.13182/NSE83-A17318
Articles are hosted by Taylor and Francis Online.
The neutron total cross sections of 249Bk and 249Cf have been measured from 0.03 to 100 eV using the Oak Ridge Electron Linear Accelerator as a source of pulsed neutrons. The 1.6-mm-diam cylindrical transmission samples initially contained up to 5.3 mg of 98% 249Bk and 2% 249Cf; 4.5 yr later, when the final measurements were made, the composition of the samples had become 2.5% 249Bk, 96.9% 249Cf and 0.6% 245Cm. Samples were cooled with liquid nitrogen to reduce Doppler broadening. Thirty-nine resonances were identified in 249Bk and analyzed using a single-level Breit-Wigner formalism. Fifty-five resonances were identified in 249Cf and analyzed using an R-matrix multilevel formalism. The resonance parameters obtained have been used to determine the average level spacings and the s-wave neutron and fission strength functions. Where possible, bound-level parameters were derived to fit the thermal neutron total cross-section data.