Title: ORNL Fusion Power Demonstration Study: Fluid Flow, Heat Transfer, and Stress Analysis Considerations in the Design of Blankets for Full-Scale Fusion Reactors.

In this brief project planning exercise, broad strategic scope and timing considerations are examined and major programmatic assumptions, driving forces, constraints, and decision points are postulated. An implementation plan for executing the program strategy is presented. Conclusions and recommendations for continued development of this approach are discussed.

A numerical simulation of coupled multiphase fluid flow, heat transfer, and mechanical deformation was carried out to study coupled thermal-hydrological-mechanical (THM) processes at the Yucca Mountain Drift Scale Test (DST) and for validation of a coupled THM numerical simulator. The ability of the numerical simulator to model relevant coupled THM processes at the DST was evaluated by comparison of numerical results to in situ measurements of temperature, water saturation, displacement, and fracture permeability. Of particular relevance for coupled THM processes are thermally induced rock-mass stress and deformations, with associated changes in fracture aperture and fractured rock permeability. Thermally induced rock-massmore » deformation and accompanying changes in fracture permeability were reasonably well predicted using a continuum elastic model, although some individual measurements of displacement and permeability indicate inelastic mechanical responses. It is concluded that fracture closure/opening caused by a change in thermally induced normal stress across fractures is an important mechanism for changes in intrinsic fracture permeability at the DST, whereas fracture shear dilation appears to be less significant. Observed and predicted maximum permeability changes at the DST are within one order of magnitude. These data are important for bounding model predictions of potential changes in rock-mass permeability at a future repository in Yucca Mountain.« less

Fusion reactors as presently contemplated are excessively complicated, are virtually inaccessible for some repairs, and are subject to frequent loss of function. This dilemma arises in large part because the closed surface that separates the ''hard'' vacuum of the plasma zone from atmospheric pressure is located at the first wall or between blanket and shield. This closed surface is one containing hundreds to thousands of linear meters of welds or mechanical seals which are subject to radiation damage and cyclic fatigue. In situ repair is extremely difficult. This paper examines the arguments favoring the enclosing of the entire reactor inmore » a vacuum building and thus changing the character of this closed surface from one requiring absolute vacuum integrity to one of high pumping impedance. Two differentially pumped vacuum zones are imagined, one clean zone for the plasma and one for the balance of the volume. Both would be at substantially the same pressure. Other advantages for the vacuum enclosure are also cited and discussed.« less

The analysis preceding and supporting the design of the cooling system of the ML-1, a mobile, low-power, nuclear power plant, is described in sufficient detail for an engineer to follow the development of the design. Test results and similar data are used to support the calculations whenever possible.