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When deployments hit setbacks: Cautionary tales in Idaho and Alaska
Plans announced with fanfare sometimes falter in the face of competition or economics. Take NuScale Power’s plans for the Carbon Free Power Project in Idaho: The project was canceled in mid-November by NuScale and its first customer, Utah Associated Municipal Power Systems, after nearly a decade. The significance of that news depends on the observer. NuScale intends to focus on other sites and customers. Competitors may redouble efforts to tout their own designs and customer lists. Media found an opportunity to speculate about the future of advanced nuclear. And while many in the nuclear community believe the momentum in favor of new nuclear deployments is continuing—or even increasing as COP28 continues—others would caution against high hopes and point to the persistent obstacles of regulation, supply chain constraints, and financing costs.
Antti Daavittila, Anitta Hämäläinen, Riitta Kyrki-Rajamäki
Nuclear Technology | Volume 142 | Number 2 | May 2003 | Pages 116-123
Technical Paper | OECD/NRC MSLB Benchmark | doi.org/10.13182/NT03-A3377
Articles are hosted by Taylor and Francis Online.
All of the three exercises of the Organization for Economic Cooperation and Development/Nuclear Regulatory Commission pressurized water reactor main steam line break (PWR MSLB) benchmark were calculated at VTT, the Technical Research Centre of Finland. For the first exercise, the plant simulation with point-kinetic neutronics, the thermal-hydraulics code SMABRE was used. The second exercise was calculated with the three-dimensional reactor dynamics code TRAB-3D, and the third exercise with the combination TRAB-3D/SMABRE. VTT has over ten years' experience of coupling neutronic and thermal-hydraulic codes, but this benchmark was the first time these two codes, both developed at VTT, were coupled together. The coupled code system is fast and efficient; the total computation time of the 100-s transient in the third exercise was 16 min on a modern UNIX workstation. The results of all the exercises are similar to those of the other participants. In order to demonstrate the effect of secondary circuit modeling on the results, three different cases were calculated. In case 1 there is no phase separation in the steam lines and no flow reversal in the aspirator. In case 2 the flow reversal in the aspirator is allowed, but there is no phase separation in the steam lines. Finally, in case 3 the drift-flux model is used for the phase separation in the steam lines, but the aspirator flow reversal is not allowed. With these two modeling variations, it is possible to cover a remarkably broad range of results. The maximum power level reached after the reactor trip varies from 534 to 904 MW, the range of the time of the power maximum being close to 30 s. Compared to the total calculated transient time of 100 s, the effect of the secondary side modeling is extremely important.