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IAEA again raises global nuclear power projections
Noting recent momentum behind nuclear power, the International Atomic Energy Agency has revised up its projections for the expansion of nuclear power, estimating that global nuclear operational capacity will more than double by 2050—reaching 2.6 times the 2024 level—with small modular reactors expected to play a pivotal role in this high-case scenario.
IAEA director general Rafael Mariano Grossi announced the new projections, contained in the annual report Energy, Electricity, and Nuclear Power Estimates for the Period up to 2050 at the 69th IAEA General Conference in Vienna.
In the report’s high-case scenario, nuclear electrical generating capacity is projected to increase to from 377 GW at the end of 2024 to 992 GW by 2050. In a low-case scenario, capacity rises 50 percent, compared with 2024, to 561 GW. SMRs are projected to account for 24 percent of the new capacity added in the high case and for 5 percent in the low case.
Michitsugu Mori
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 260-274
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2838
Articles are hosted by Taylor and Francis Online.
The benchmarking and qualification analyses of RETRAN-03 (RETRAN-3D) for boiling water reactor (BWR) stability analyses were carried out by comparison with the frequency-domain stability analysis code NUFREQ-NPT with the stability test data of the Peach Bottom Unit 2. The sensitivities of model parameters were studied in terms of the type of equation model, vapor-liquid interface heat transfer coefficient in upper downcomer, method of characteristics (MOC) model, proportionality constant in the pressure change mass transfer term, and nodalization of a core for the turbine trip test analyses. The sensitivity studies of the model parameters to the decay ratio in stability analyses were performed on the number of core channels, type of equation model, nodalization of a core, perturbation type of disturbance, slip model, proportionality constant in the pressure change mass transfer term, Courant number, MOC model, and kinetics model. The models were selected for the turbine trip tests analyses and for stability tests analyses, based on the sensitivity studies. The model used to analyze stability in RETRAN-03 adopted the five-equations with the MOC, and two-channel models for the core heating region divided into 40 nodes despite 24 nodes used for the turbine trip test analyses. The validation of the model was confirmed by the analyses of the turbine trip tests of the Peach Bottom Unit-2. The stability analyses with the test data and the benchmarking of RETRAN-03 compared with the frequency-domain stability analysis code NUFREQ-NPT in BWR stability exhibit verification and validation within the applicable limitation of the code.
