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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.
Luis E. Herranz, Jesús Polo
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 168-176
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34973
Articles are hosted by Taylor and Francis Online.
The significance of iodine for source term quantification has been studied by investigating its chemical behavior under the prototypical conditions of a hypothetical severe accident within the containment. As a result, some computer codes were developed and their validation is currently under way. The loss-of-fluid test (LOFT) program was one of the most relevant research projects in the area of nuclear safety. Its last experiment, LP-FP-2, simulated a V-sequence. A great deal of information was recorded on the fission product release, transport, and deposition. A theoretical approach to the chemical behavior of iodine in the blowdown suppression tank (BST) of the LOFT facility was attempted with the IODE and IMPAIR-2/M codes. The comparison of the predictions with the existing experimental data led to the conclusion that the BST system behaved as a low-volatility system, with most of the iodine in the form of the soluble nonvolatile species iodide. Only a partial conversion to volatile molecular iodine was observed due to the presence of radiation. However, the intensity of the γ field was so weak that this transformation was not quantitatively meaningful.