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From the pages of Nuclear News: Industry update September 2024
Here is a recap of industry happenings from the recent past:
BWXT advanced nuclear reactor agreement signed
Burns & McDonnell, a family of construction and design companies, has entered into an agreement with BWX Technologies to further advance the design and development of the BWXT BANR microreactor, which has a “passively safe design” for powering remote facilities while providing a carbon-free source of heat and electricity. The two companies completed the first phase of their collaboration in early 2024 and intend to complete the second phase by the third quarter of 2025. Burns & McDonnell is helping BWXT develop the balance-of-plant systems for the BANR, generate the power plant layout, and perform preconstruction planning. Its scope of work also includes developing power cycle architecture, identifying critical components, integrating site design, and supporting steam and power distribution infrastructure and reactor building structures. The Wyoming Energy Authority is currently evaluating the feasibility of using the BANR in a state nuclear market for baseload heat and power deployed for remote industrial users, such as mining operations.
Richard F. Farman, Charles E. Hendrix, Jason Chao
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 84-93
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33666
Articles are hosted by Taylor and Francis Online.
Two simulations of pressurized water reactor (PWR) anticipated transient without scram (ATWS) sequences were performed in the loss-of-fluid test (LOFT) facility. These were designated as tests L9-3 and L9-4. Test L9-3 is a loss-of-feedwater transient, while L9-4 simulates an ATWS accompanied by loss of off-site power. In the latter case, the main steam valve and primary circulation pumps are tripped at the beginning of the experiment, along with the steam generator feedwater flow. The behavior of these experiments was analyzed with the RETRAN-02 computer code in order to evaluate the capability of the code to predict A TWS behavior against the experimental evidence exhibited by LOFT. The complex sequence of events, which occurs in L9-3, creates a difficult system modeling problem. The primary influence on the entire system response is the steam generator heat transfer rate (given core power as a boundary condition). Results of the analysis demonstrate how the course of the computer calculation is influenced by the steam generator model and its initial conditions. Test L9-4 does not contain the thermal-hydraulic complexity of test L9-3 due to the immediate isolation of the steam generator. Nonetheless, it reinforces the general conclusion that RETRAN-02 will produce an adequate simulation of PWR ATWS behavior if the initial and boundary conditions are completely defined.