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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Byong-Jo Yun, Dong-Jin Euh, Chul-Hwa Song
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 56-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3773
Articles are hosted by Taylor and Francis Online.
Hydraulic phenomena in the downcomer of a conventional pressurized water reactor have an important effect on the transient evaluations of a postulated large-break loss-of-coolant accident (LBLOCA). In particular, safety analyses using best-estimate codes show that downcomer boiling is one of the important phenomena in the postulated LBLOCA because it can degrade the hydraulic head in the downcomer and consequently affect the reflood flow rate for core cooling. To experimentally identify the thermal-hydraulic behavior in the downcomer, a downcomer-boiling test facility was constructed for simulating downcomer boiling in the reflood phase of a postulated LBLOCA.The test facility was designed by adopting a full-pressure, full-height, and full-size downcomer-gap approach but with the circumferential length reduced 47.08-fold. The test was divided into two phases: (a) visual observation and acquisition of the global two-phase flow parameters and (b) measurement of the local two-phase flow parameters.This paper presents the test results from Phase I. The major measured parameters were the axial void fraction and the fluid temperatures and pressures in the test section. The measured data were used to evaluate a safety analysis code, MARS 2.1b, to investigate its modeling accuracy and identify weaknesses of the thermal-hydraulic models therein.