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Latest News
BWRX-300 SMR passes U.K. regulatory milestone
GE Vernova Hitachi Nuclear Energy’s BWRX-300 small modular reactor has completed the second step of the generic design assessment (GDA) process in the United Kingdom. In this step, the U.K. Office for Nuclear Regulation, the Environment Agency, and Natural Resources Wales did not identify “any fundamental safety, security safeguard or environmental protection shortfalls with the design of the BWRX-300.” Step 1 was completed in December 2024.
Tien-Ko Wang, Jun Hsin, Min Lee
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 287-296
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34453
Articles are hosted by Taylor and Francis Online.
A series of MAAP3.0 calculations was made with varying parameters to simulate a postulated large-break loss-of-coolant accident at the Kuosheng plant with a boiling water reactor-6 and MARK III containment. Analyses showed that uncertainties in the corematerial eutectic temperature and the degree of flow blockage will result in a large uncertainty in the predicted in-vessel hydrogen generation. The pressure variations caused by hydrogen burns, which are related to the preceding in- and ex-vessel hydrogen generation, may force some suppression-pool water into the pedestal cavity where most of the corium remains. This will further affect the possibility and the extent of corium/concrete interactions and thus the rate and the amount of ex-vessel hydrogen generation. Burns would occur at a very low hydrogen concentration if the compartment (gas) temperature were high and the flame temperature criteria were used for burn determination. If burns were to occur after containment failure, the hydrogen burns could have a significant impact on the release of fission product to the environment.