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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.
Marko Maucec, Matjaz Ravnik, Bogdan Glumac
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 255-264
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2867
Articles are hosted by Taylor and Francis Online.
A criticality safety study of various forms of multiplying medium based on RBMK-1000 fuel elements is presented. The calculations were performed with the Los Alamos National Laboratory Monte Carlo MCNP4B code. Continuous energy cross-section data have been taken from the ENDF/B-VI and ENDF/B-V libraries and S(,) scattering functions from the ENDF/B-IV library. A detailed three-dimensional model of the RBMK fuel element has been developed. A set of parametric calculations was performed for some hypothetical fuel conditions with the infinite model of storage lattice. Multiplying properties of homogenized mixture of fuel and moderator were also analyzed. Certain combinations of moderator (graphite-water mixture) and fuel may yield a significantly increased multiplication factor with respect to normal reactor lattice conditions. MCNP calculations were performed for fresh fuel conditions. The reduction of the multiplication factor due to burnup up to 20 GWd/TU was estimated using the WIMS/D-5 code for lattice-cell conditions. It was observed that the multiplication factor (kinf or keff) does not exceed unity if the burnup is taken into account regardless of the assumptions on the fuel conditions.