gmax137 said:
I don't recall ever seeing a full-plant design concept. I mean aside from the particle physics and magnets. How do you get the heat out? Do you boil water and use a Rankine steam plant to turn the generator?
Once upon a time (late 1970s, early 1980s), there was a STARFIRE commercial fusion reactor concept.
STARFIRE reference commercial tokamak fusion power reactor design
https://www.osti.gov/biblio/6187212...ommercial-tokamak-fusion-power-reactor-design
STARFIRE: a commercial tokamak fusion power plant study
Volume I, Chapter 1-11, ANL/FPP-80-1 -
https://www.osti.gov/biblio/6679109-starfire-commercial-tokamak-fusion-power-plant-study
Volume II, Chapter 12-23 and Appendices -
https://www.osti.gov/biblio/6633213-starfire-commercial-tokamak-fusion-power-plant-study
From Volume I, 2.3.1 Reactor Configuration (page 46 of 875 in pdf).
The reactor delivers 1200 MWe to the grid in addition to providing 240 MWe for recirculating power requirements. The reactor operates with a continuous plasma burn and develops 4000 MW of useful thermal power.
A lot of wishful thinking went into that.
And there is this -
https://fti.neep.wisc.edu/fti.neep.wisc.edu/ncoe/timeline/mfe/US22b1.html
and more recently -
https://www.engr.wisc.edu/news/uw-m...or-fusion-energy-research-at-wendelstein-7-x/
And that is just one university. There are other university programs, e.g., Princeton, MIT, . . . .
A lot has happened since then, and the funding situation for fusion research is considered volatile for any given institution. U of Wisconsin was kind of a leader until they weren't, and it was not unique to UW.
Archived site for U of Wisconsin, Fusion Technology Institute.
https://fti.neep.wisc.edu/fti.neep.wisc.edu/index.html 
from:
https://energy.wisc.edu/research/uw...versity-wisconsin-fusion-technology-institute
Since then, the cost of raw materials has increased. I attended separate meetings with AREVA/Framatome, GE (GEH) and Westinghouse back around 2000 during which presentations were made on their next generation (Gen-III+) LWRs. An estimated cost was about $1 billion per unity. A few years later it was about $2 billion per unit, then by the end of the decade about $5 billion to $7 billion, and that is with government guarantees and subsidies. As of about 2019/2020, "Units 1–2: $8.87 billion (1989 USD) ($16.2 billion in 2019 dollars)
Units 3–4: $25 billion (estimated)", or about $12.5 billion per unit, and they are not quite finished. Similarly, the costs for the EPR in Europe, Olkiluoto 3 and Flamanville 3, were WAY over budget. Both Westinghouse and AREVA were driven into bankruptcy (for these plants and other problems) and were restructured. Ref:
https://en.wikipedia.org/wiki/Vogtle_Electric_Generating_Plant
gmax137 said:
Unlike a fission plant, it seems to me you wouldn't need the containment, or all of the core-flooding and decay heat removing safety systems (and their supporting systems, emergency diesels, safety grade ultimate heat sink, redundant controls, on and on). Not only avoiding those construction costs, but also the monthly surveillance testing on all that stuff throughout the plant life.
With no fissionable materials on site, you don't need a huge security staff.
There is no fission, unless they put a breeding blanket of
238U on the periphery. There have been fusion-fission hybrid concepts. Even without fission, one may have large quantities of tritium both as a fuel and as a product. For d+d -> t + p, roughly about 50% of the time. That has to be contained somehow. They could also breed T in blankets of Li, which requires a secured facility.
The containment building has to withstand any hypothetical accident, e.g., a magnet quench, or other fault. For example, Superconducting Magnet Explosion
https://ehs.berkeley.edu/news/superconducting-magnet-explosion
A 9.4 Tesla superconducting magnet, used for mass spectroscopy in a campus laboratory recently suffered a catastrophic failure. The incident was apparently caused by over-pressurization and failure of the liquid helium (LHe) chamber. Although there were no injuries because the incident occurred during off-hours, the potential for significant injury due to the venting of LHe into the facility was present. There was also significant damage to equipment associated with the magnet.
A magnet achieves superconductivity (zero resistance to electrical current) when it is bathed in LHe. If for some reason the magnetic coil starts to resist the electrical current, it heats up, causing an explosive expansion of the LHe. This expansion of gas is vented through a large bore vent, sealed by a membrane called a "rupture disk". This process of explosive venting is known as a "quench".
It is a concern but on a larger scale for a power reactor system.
gmax137 said:
What does that translate into in $/MW-hr? And how much energy does it take to create the "fuel grade" D2?
I think I was editing my post when you quoted. I had raised my cost estimate for D
2 to more than $1000/kg.
I'll have to do some calculations, and look into the second question. Obviously, the Canadians produce copious amounts of deuterium for the heavy water CANDU reactors.
As an undergrad and graduate student, I was keen on fusion and fast reactor technologies. Professionally, I ended up working mostly in LWR technology (fuel and core components, and materials) and some special nuclear applications.