A-SMR concept evaluations

The DOE is initiating preliminary work via its labs on concept studies for three A-SMR technologies: (1) the advanced sodium-cooled fast reactor with a design electrical rating of 100 MWe (AFR-100) with Argonne National Laboratory as the lead, (2) a generic small HTGR concept derived from the three HTGR designs evaluated under DOE’s NGNP program with the Idaho National Laboratory as the lead, and (3) a small fluoride salt-cooled reactor, the small, modular, advanced high-temperature reactor (SmAHTR) that is graphite moderated with a design electrical ratings of 20 or 50 MWe with Oak Ridge National Laboratory as the lead.

The initial efforts on all three concepts will focus on two objectives: (1) prepare a brief description of the reactor design in terms of major design features and attributes as a reference design and (2) conduct a technology readiness assessment of the important technologies to provide a status of these technologies and a sense of the R&D that would be needed to develop a commercial design.

image175 image176

Figures 14.5 and 14.6 present illustrations of pre-conceptual designs for the AFR-100 [9] and SmAHTR [10] concepts, respectively, while Tables 14.5 and 14.6 provide basic design system parameters for each concept.

Primary — heat

Подпись: DRACS heat exchanger Подпись: Core barrelПодпись: Figure 14.6 SmAHTR fluoride salt-cooled A-SMR concept [10].image180exchanger

Table 14.5 AFR-100 design parameters

Parameter

Value

Reactor power (MWt/MWe)

Fuel form/enrichment Average power density (kW/l)

Core diameter/height (in)

Core inlet/outlet temperatures (°C) Primary coolant

Coolant flow rate gallons per minute Passive decay heat removal Transportable via rail/truck

250/100

Uranium-Zirconium/13.5%

64.3

118/166 (3/4 m)

395/550

Sodium

5864

Three 0.25% loops Yes