
Flying pigs pose a greater menace to air safety than bird strikes do.

On the job training is good for the worker but deadly for the job. A job gets done when there is a guy on it that has done it one hundred times before; he can do it in his sleep. That is how jobs succeed, on time and under budget.- Axil
All the money that will be spent on renewables is supposed to create lots of green jobs. Coal miners and auto workers will be retrained to make the promise of all the green technologies come true. The problem is that there are few capable engineers left to do all the work that is required. The youth of the country has opted for money making low stress jobs on Wall Street and in regional banking.
The only way to maintain competent engineers is through investment in technology research and development. Because of the parasitic business practices that have been pervasive since the 90’s, a destructive corporate attitude toward engineering has eaten a large hole in the nation’s science and engineering capability. American business has shipped its software, engineering and scientific base offshore primarily to Asia to reduce associated local wage rates.
Young people see what is going on and choose finance, law and other well paying but parasitic professions as their life’s work while the engineering profession withers on the vine.
Making things is out, making money is in.
American business has been eating the seed corn of its prosperity and now it is gone. The captains of American industry decry the lack of on shore US technical capability and at the same time outsource whole business lines to Asia. They then are surprised when Asia beats them to death through their own home grown engineering excellence.
Obama wants his green money to fund green American jobs, but that’s not how it works today in America.
The chickens have come home to roost. America is now an empty shell of accountants, lawyers and bankrupt financiers. A generation of profound pain, of relearning, failed systems, of reappraisal and of business evolution is ahead. A twenty year period of retrenchment will precede a philosophical shift and business readjustment before a rebirth of American engineering competence is common again in America. The smart grid won't happen anytime soon; but it might work if we off shore it to China.

EEStor, Inc. Announces Relative Permittivity Certification of 2009-04-22 19:49:36.589 GMT
EEStor, Inc. Announces Relative Permittivity Certification of Their Composition Modified Barium-Titanate Powders
PR Newswire
CEDAR PARK, Texas, April 22
CEDAR PARK, Texas, April 22 /PRNewswire/ -- EEStor, Inc. announces relative permittivity certification of their Composition Modified Barium-Titanate powders. The third party certification tests were performed by Texas Research International's Dr. Edward G. Golla, PhD., Laboratory Director. He has certificated that EEStor's patented and patent pending Composition Modified Barium-Titanate Powders have met and/or exceeded a relative permittivity of 22,500.
EEStor feels this is a huge milestone which opens the advancement of key products and services in the electrical energy storage markets of today. The automotive and renewable energy sectors are a few of the key markets that would benefit greatly with the technology.
Company background
EEStor, Inc. develops solid-state electrical energy storage units (EESU's) in the form of batteries and capacitors. This technology has a wide variety of application use which includes with the added benefit of being longer lasting, lighter, more powerful, and more environmentally friendly than current technology in use.
SOURCE EEStor, Inc.
Contact: Richard D. Weir, President and CEO of EEStor, Inc., +1-512-259-7601, Info@eestor.us -0- Apr/22/2009 19:49 GMT
The BIG savings, IMHO, is not necessarily on the ability to using the existing turbine/generator set. It's on all the other BOP (Balance of Plant). What are we talking about?
1. siting. already done, obviously.
2. grid access...with almost NO changes especially if generator at the end of the LFTR is the same size or near it as the old stoker it's replacing. A little more if we want to upgrade the MWs.
3. licenses for everything: accumulation of standard hazardous waste, water usage, fire fighting equipment, water discharges, maybe cooling towers, air cooled condensers, once through cooling. The list is endless and it's all a *savings*.
4. plant access by road, rail and water. All these are nicely built in because of the need to transport coal and having built the plant in the first place.
5. lay down yard. As the coal is reduced by burning, more and more of the dozens of acres of land used by coal storage areas is freed up. Tons and tons of space.
6. Physical equipment: water lines to and around the plant, bus rooms and switching centers for plant auxiliaries, main and aux. banks *in place and ready to use*.
Probably the savings list is endless.
The BIGGEST advantage we have for a LFTR-in-Coal-out scenario is just that. We when we go COD on the LFTR, the breaker opens for the last time on the stoker, and we closed out a coal plant. Let wind and solar advocates try to make THAT claim!A second major keynote to the LFTR is its modularity. Contributer Axil notes:
In systems engineering, modular design, or "modularity in design" is an approach that subdivides a system into smaller parts (modules) that can be independently created and then used in different systems to drive multiple functionalities. Besides reduction in cost (due to lesser customization, and less learning time), and flexibility in design, modularity offers other benefits such as augmentation (adding new solution by merely plugging in a new module), and exclusion.Some Energy from Thorium contributers are more influenced by French thinking on the TMSR. David LeBlanc suggests
Modular design is much more difficult to design and implement then a custom build approach since it requires the systems engineer to examine the full range of possibilities of a product line and define modules and appropriate interfaces between these modules.
A key feature of a system is that it is modular, flexible and adaptable. In general, it is commonly recognized in systems engineering that the broader the range of adaptability that a system is, the more successful and cost effective that the system will eventually be. These characteristics of the system ensure that the system is responsive to the needs of its broad user base over time. A good system must meet or exceed the expectations of a large and diverse range of users.
For example, a computer is divided up into a mother board, disks, CPU, internet interface, etc. A computer that does not provide this level of modularity will be unsuccessful in the market place since it does not offer the possibility for upgrade.
IMHO, it would be a good thing if the Lftr were modular.
What will make the Lftr modular, and how is that modularity achieved? It would be valuable to develop a consensus that modularity of design is an important design objective and that it is worth the effort to make the design modular.
A graphite free core design does not necessarily need a much larger fissile inventory to start up IF you have a nice fully encompassing fertile blanket around the core to catch leakage neutrons.Alex P., quoting ORNL 4812 disagreed with him:
In reactors without graphite, the neutrons can travel quite a long way before they finally are absorbed (or lost to leakage). Thus in designs without a blanket or only a partial one (as is the French TMSR design) you need a lot of fissile material to make sure those neutrons are absorbed and/or cause fissions quickly. If you have a full fertile blanket as is the case in some other designs then you can actually get by with a much lower fissile starting load and still manage to break even on breeding.
So no graphite equaling much more fissile is not always the case (granted it usually is).
Also I would add that the positive temp reactivity problem with using graphite is not a problem for 2 fluid designs (as most know) AND it is also not a problem for Single fluid designs with U238 added to denature (which most don't know).
contrary to my previous belief, breeding gain in the epithermal spectrum is INFERIOR than in the thermal one.
Quite the opposite I believed it happened.
http://www.energyfromthorium.com/pdf/ORNL-4812_chap2.pdf
"In the early days of the Molten-Salt Reactor Program, serious consideration was given to homogeneous reactors in which the core contained nothing but salt. These ideas were abandoned after calculations showed that the limited moderation by likely fluoride salt constituents alone would result in a thermal reactor with inferior breeding performance. Breeding appeared possible in intermediate-spectrum reactors, but their gains were not high enough to compensate for their higher fissile inventories".

THE THORIUM MOLTEN SALT REACTOR: LAUNCHING
THE THORIUM CYCLE WHILE CLOSING THE CURRENT
E. MERLE-LUCOTTE, D. HEUER, M. ALLIBERT, V. GHETTA,
C. LE BRUN, R. BRISSOT, E. LIATARD, L. MATHIEU
LPSC, Université Joseph Fourier, IN2P3-CNRS, INPG
LPSC, 53, avenue des Martyrs, F-38026 Grenoble Cedex - France
ABSTRACT
Molten salt reactors, in the configuration presented here and called Thorium Molten Salt Reactor
(TMSR), are particularly well suited to fulfil the criteria defined by the Generation IV forum, and
may be operated in simplified and safe conditions in the Th/233U fuel cycle with fluoride salts. The
characteristics of TMSRs based on a fast neutron spectrum are detailed in this paper, focusing on
their excellent level of deterministic safety. We aimed at designing a critical TMSR able to burn
the Plutonium and the Minor Actinides produced in the currently operating reactors, and
consequently to convert this Plutonium into 233U. This leads to closing the current fuel cycle
thanks to TMSRs started with transuranic elements on a Thorium base, i.e. started in the Th/Pu
fuel cycle. We study the transition between the reactors of second and third generations to the
Thorium cycle in a European frame. -
------------------------------------------------
Conclusion
The Thorium Molten Salt reactor (TMSR) presented here with no moderator in the core appears as a
very promising, simple and suitable concept of molten salt reactor. The non-moderated TMSR
configurations considered in this paper, based on a fast neutron spectrum, present particularly
interesting characteristics. Their deterministic safety level is excellent. They can be started with a fuel
made from the TRU wastes produced in current LWRs. Their rather large initial fissile inventory does
not prevent fast deployment thanks to their good 233U breeding. The technology which in principle
does not involve the transportation of radioactive materials outside the reactor site as well as the
presence of 232U within the fuel can be considered as restricting proliferation risks.
The concept itself has some appealing aspects compared to earlier versions of MSRs. The reactor core
is extremely simple. Simulation calculations do not point to major reprocessing constraints. In
particular the fluxes considered should allow the batch mode reprocessing to be installed in the
vicinity of the reactor. Initial studies of the scientific feasibility of the on-line control of the salt
composition and of its chemical and physical properties have not unearthed a showstopper.
When it comes to Generation-4, it appears that the major nuclear energy powers have given a higher
priority to the SFR concept. This mostly reflects a justified confidence in a technology which,
although it has not yet reached all the performances expected for a GEN-4 reactor, has already been
successfully tested in numerous projects. But all the properties detailed in this paper, especially its
deterministic safety performances and its ability to reduce the radio-toxicity of wastes currently
produced, put the TMSR in a very favourable position to fulfil the conditions defined by the GEN IV
International Forum. Moreover this TMSR concept may be very appealing to countries which hold
important thorium resources and have some remaining adjustment margins in the definition of their
nuclear energy policy. The TMSR is thus an excellent candidate to produce the large amounts of
nuclear energy that the world will need in the near future.
1. The ability to produce LFTR's with at leasr a one to one conversion ratio. That is the bility to produce as much nuclear fuel as they consumeThe conversion ratio would be a matter of LFTR design. But there is a potential constraint on the required input of fissionable materials to start the LFTR. In all reactors moderators act to increase reactivity. The best moderators are heavy water and graphite. Early reactors which used natural uranium as fuel required either graphite or heavy water as moderators. Light water is a significantly less powerful moderator than either graphite or heavy water. Graphite moderated reactors require a significantly smaller start up charge - perhaps 25% or even less fissionable material to achieve criticlity. Unmoderated reactors require far more fissionable material in order to maintain a chain reaction. It LFTRs the carrier salts function as partial moderators. Thus it is possible to operate a LFTR without graphite, but its opperation will require a far larger inventory of fissionable materials. That means more fissionable materials for the start up charge. Thus the use of graphite would be an emportant componant of LFTR scalability. It would be possible to build a large number of LFTR's without but that would require consideably more enriched U-235 or more U-233 or more Pu-239. Thus the use of Graphite in LFTR's would be highly desirable.
2. The availability of as much fissionable start up charges as would be required by large scale deployment.
This concerns in particular how the graphite reacts to irradiation exposure. Beyond a certain degree of damage, it becomes the seat of swelling. Graphite’s life span is determined bythe time it takes to reach a fluence limit,In addition to the well known problem with graphite swelling, French researchers (L. Mathieu,D. Heuer, R. Brissot, C.LeBrun, E. Liatard, J.-M. Loiseaux, O. Méplan, E. Merle-Lucotte, A. Nuttinand, J. Wilson, C. Garzenne, D.Lecarpentier, and E.Walle) believe that they had spotted another problem with graphite. They descrabed the classic ORNL graphite moderated MSBR:
Our standard system is a 1 GWe graphite moderated reactor. Its operating temperature is 630 C and its thermodynamic efficiency is 40 %. The graphite matrix comprises a lattice of hexagonal elements with 15 cm sides. The total diameter of the matrix is 3.20 m. Its height is also 3.20 m. The density of this nuclear grade graphite is set to 1.86. The salt runs through the middle of each of the elements, in a channel whose radius is 8.5 cm. One third of the 20 m3 of fuel salt circulates in external circuits and, as a consequence, outside of the neutron flux. A thorium and graphite radial blanket surrounds the core so as to improve the system’s regeneration capability. The properties of the blanket are such that it stops approximately 80 % of the neutrons, thus protecting external structures from irradiation while improving regeneration. We assume that the 233 U produced in the blanket is extracted within a 6 month period.They noted something that appeared to have escaped ORNL researchers. As the heat of graphite increases a positive coefficiency or reactivity effect,
They note the importance of the size of channels in the graphite:
The size of the channels in which the salt circulates is a fundamental parameter of the reactor. Since the size of the hexagons is kept constant in all of our studies, the size of the channels determines the moderation ratio. Changing the radius of the channels modifies the behavior of the core, placing it anywhere between a very thermalized neutron spectrum and a relatively fast spectrum. The cross section resonances of the materials present in the corehave a strong impact on the neutronic behavior of the reactor.
comes from an energy shift of the thermal part of theneutron spectrum(around 0.2eV), due to heating of the moderator. This shift increases the fission rate because of a smalllow energy(0.3eV) resonance in the fission cross section of 233U. It simpact on the stability decreases as the amount of graphite in the core decreases and as the influence of th ethermal portion of the spectrum weakens.Now if you are a really cool cat, you know that this means that there is a potential reactor safety problem related the heating of graphite in a reactor in which U-233 is being burned. Sacre bleu! But getting rid of the graphite helps. But what the French researchers are really trying to say is, if you build a 1 GW Graphite moderated MSR and run it at full blast, you are going to shorten the lifespan of the graphite moderator, by subjecting it to a lot of neutron radiation and heat. Furthermore heating the graphite creats an effect that makes the reactor less safe.
Since the safety aspect cannot be circumvented in the design process of a nuclear reactor, we consider that this constraint is necessarily satisfied. Moreover, we consider only those configurations whose total feedback coefficient, not just the salt feedback coefficient, is negative. Except in the case where the size of the reactor is reduced dramatically, leading to a significantly increased neutron flux, the total feedback coefficient is negative only for either very thermalized or fast neutron spectra. The first option implies a small fissile matter inventory and a weak neutron flux. When submitted to such a flux, the graphite undergoes little damage and its life span is reasonably long.Thus the French researchers tell us:
On the other hand, captures in the moderator deteriorate the breeding ratio significantly. If a reactor system does not need to regenerate its fuel, then this very thermalized configuration may be suitable.
Decreasing the specific power of the reactor (by increasing its size and/or decreasing the total power generated) leads directly to a decreased flux intensity and, as a consequence, extends the graphite’s life spanThey add:
This, however, increases in the same proportion the per GWe fissile matter inventory, without providing a very satisfactory solution.Now ir sounds like the French want to get rid of the graphite real bad. But note that their study focused on a 1 GWe reactor - the MSBR - opearating at 630 C. But there is an exception if the reactor were dramatically smaller. I wonder if say 100 MWe would be considered dramatically smaller in France.
The French operate their electrical grid with a bunch of huge reactors. They do not run air conditioners in the summer, and if there is an August heat wave, a whole lot of old French men and women are going to die. In Texas we value our old people, and want to keep them around, so we have a big summer electrical reserve. I maintain that any acceptable solution to the energy crisis will keep my air conditioner running all through the Dallas summer. In Texas now the reserve power generators run on natural gas. it would b nice to switch that system to nuclear. Big French reactors won't do the trik, because they cost tooo much, but little LFTR's that generate 100 MWe would do the trick, and they don't have to run real hot for efficiency. It would be a blessing if Kirk Sorensen would design one that could be built and operated at a low price. Now Kirk has not spelled out details to me, but I'll bet he has got a few tricks up his sleave, that would give a graphite moderator a reasonably long life, and will take care of those safety issues that have so worried the French."the fast breeder arrived first and was therefore able to consolidate its political position within the AEC. But there was another, more technical reason. The molten-salt technology is entirely different from the technology of any other reactor. To the inexperienced, molten-salt technology is daunting. This certainly seemed to be Milton Shaw's attitude toward molten salts—and he after all was director of reactor development at the AEC during the molten-salt development. Perhaps the moral to be drawn is that a technology that differs too much from an existing technology has not one hurdle to overcome—to demonstrate its feasibility—but another even greater one—to convince influential individuals and organizations who are intellectually and emotionally attached to a different technology that they should adopt the new path. This, the molten-salt system could not do. It was a successful technology that was dropped because it was too different from the main lines of reactor development.
"Nuclear plants are sitting ducks for terrorists.You see there, either the fellow is not very smart, or he thinks that the readers of the Johnson's Wall Street Journal are not very smart. Needles to say Redford ran into a buzz saw of criticism from WSJ online readers who commented on the post. But David Ahlport, a self styled progressive who has offered a guest post on Joe Romm's Climate Progress offered the classic counter-factual ant-nuclear arguments:
It’s the most expensive way to essentially boil water.
There’s the waste issue,
there’s nuclear proliferation,
the subsidies".
A. The federal money spend on nuclear waste and anti-proliferation, gigantically dwarfs all total federal spending on EnergyOh wow David, I thought that the reactor operators were were paying the Federal Government to take care of their nuclear waste, and that the government wasn't living up to its end of the deal. So the reactor operators are not paying a second time to store the same waste they are paying the government to store. Now is David confused or is he lying about who pays for nuclear waste?
B. Nuclear can’t provide it’s own private capital financinglast time I checked every wind and solar project in the United States receives federal and state subsidies, including in the case of solar projects rather large very large federal subsidies for investments. In contrast, the nuclear investors receive loan guarantees that do not cost tax payers money unless the investors default on their borrowing.
C. Nuclear provides very little of it’s own R&D financingfact research and development for the current generation of nuclear plants was paid for by the reactor manufacturers, not the federal government. At any rate all the reactor manufacturers are foreign owned, and of course if the governments of those countries pay for reactor R&D why then Americans get the benefit without paying anything.
The citing + construction of Nuclear power plants is very slow (i.e. Next batch of US reactors aren’t expected until 11 years from now, at the earliest.)The 11 year perspective is a little long, but it does take the NRC 42 months to approve a nuclear license, and Westinghouse estimates that it takes 3 years to complete construction of an AP-1000 Reactor. We are not going to see any reactor construction begin before 2012 or be complete before 2015, but this is hardly disastrous. The last time I checked there was a five year backlog on new windmill orders, so that means that a wind project that is put on the drawing boards today is not going to get built until 2015. So when Ahlport tells us:
Nuclear is only a viable option if Time and Money aren’t considered to be important.he ignores the fact that renewable energy generation sources cost money too, and do not appear when his fairy godmother waves her magic wand.
In some respects the LFTR does not qualify as a black swan. Certainly not by Nassim Nicholas Taleb's standards. Its emergence was far from random. There could scarcely be a better provenance for a reactor idea than to have been first proposed by Eugene Wigner, Alvin Weinberg and Gale Young in 1945. To this we have to add the contributions of Harold Urey. Raymond C. Briant, Ed Bettis, and many others. I would also add my father, C.J. Barton, Sr., to the list. An idea whose fathers included to Nobel-prize winning scientists and the patent holder for the light-water Reactor can hardly be considered highly improbable. It was however, daring, and once Alvin Weinberg's other invention, the light-water reactor, entered popular culture, along with the reactor dome and cooling tower, the liquid core reactor concept became something of an aberration in the folk concept. After all the worse thing could happen to a reactor was a core melt down, and now those crazy Oak Ridge scientists were trying to melt the reactor's core deliberately.Two very different schools of reactor design have emerged since the first reactors were built. One approach, exemplified by solid fuel reactors, holds that a reactor is basically a mechanical plant; the ultimate rationalization is to be sought in simplifying the heat transfer machinery. The other approach, exemplified by liquid fuel reactors, holds that a reactor is basically a chemical plant; the ultimate rationalization is to be sought in simplifying the handling and reprocessing of fuel.Briant and Weinberg added:
At the Oak Ridge National Laboratory we have chosen to explore the second approach to reactor development. . . . it has long been recognized that a liquid fuel which did not require high pressure, in which thorium or its compounds could dissolve, and which did not decompose under radiation would indeed be a major invention for the reactor art. . . .
we have been investigating another class of fluids which satisfies all three of the requirements for a desirable fluid fuel: large range of uranium and thorium solubility, low pressure, and no radiolytic gas production. These fluids, first suggested by R. C. Briant, are molten mixtures of UF4 and ThF4 with fluorides of the alkali metals, . . .
intrinsic [Molten Salt] reactor characteristics address current concerns about waste management, fissile resources, safety, and economics.


Don Carlo - Giulio Gari
Filippo II - Jerome Hines
Rodrigo - Robert Merrill
Il Grande Inquisitore - Hermann Uhde
Un Frate - Louis (Luigi) Sgarro
Elisabetta di Valois - Leonie Rysanek
La principessa Eboli - Blanche Thebom
Tebaldo - Madelaine Chambers
Il Conte di Lerma - Robert Nagy
Un Araldo Reale - William Olvis
Una voce dal cielo - Martina Arroyo
The objectives of this activity are: (I) to develop the conceptualBecause the line of research document led by ORNL-4528, its intent was not to offer clues for future development, but to document a terminated line of research. Many ORNL scientists, including my father, were not in agreement with the decision to abandon the two fluid approach, their continued believe in the soundness of their views, may have motivated the desire to document the modular two fluid design.
design for a commercial 1000 MW(e) MSBR in sufficient detail to identify the major areas im which additional technology development is required and to produce meaningful estimates of the nuclear and economic performances of this reactor type, (2) to develop the design criteria and conceptual design for a molten-salt demonstration reactor that will provide the information necessary for construction of commercial MSBRs in sufficient detail to identify additional technology development which is required for construction of the demonstration reactor and to provide improved estimates of the capital and operating costs for the demonstration reactor, (3) to develop the design criteria and conceptual design for a molten-salt test reactor in sufficient detail to identify additional
technology development which is required for construction of the test reactor and to provide improved estimates of the capital and operating costa for the test reactor, and (4) to develop the design criteria and conceptual design for a molten-salt teat reactor mockup in sufficient detail to identify additional technology development which is required for construction of the test reactor mockup and to provide improved estimates of the capital and operating costs for the mckup.
An additional important objective of this activity is the examination of alternate reactor types such as molten-salt converter reactors using uranium or plutonium fuel makeup as well as uses for molten-salt reactors other than large central station electric power generation in sufficient detail to assess the likely economic importance of alternate molten-salt reactor types. Limited conceptual design work would be carried out on alternate reactor types which show promise.
ORNL-4528
UC-80 - Reactor Technology
TWO-FLUID MOLTENSALT BREEDER REAmOR DESIGN STUDY
(STATUS AS OF JANUARY 1, 1968)
R. C. Robertson
R. B. Briggs
O. L. Smith
E. S. Bettis
ABSTRACT
A conceptual design study of a 1000 Mw(e) thermal breeder power station based on a two-fluid MSBR was commenced in 1966 as part of a program to determine whether a molten-salt reactor using the thorium-U-233 fuel cycle could produce electric power at sufficiently low cost to be of interest and at the same time show good utilization of U.S. nuclear fuel resources. This report covers the progress made in the study up to August 1967, at which time the two-fluid MSBR work was set aside in order to study a single-fluid MSBR concept. The latter became of interest at that time due to the discovery that protactinium and other fission products could be separated from a uranium-and-thorium-bearing fuel salt by reductive extraction into liquid bismuth.
The two-fluid MSBR is graphitemoderated and -reflected, with a 'LiF-BeFz-UFe fuel salt circulated through the core and a 'LiF-ThF4-BeF2 blanket salt circulated through separate flow channels distributed throughout the core, as well as in a surrounding under moderated region. The fissings raise the temperature of the fuel salt to about 1300 F and that of the blanket salt to about 1250 F. Heat is removed from the salts in shell-and-tube heat exchangers to raise the temperature of a circulating NaBF4-NaF coolant salt to about 1150°FbThe co$ant salt transports the heat to steam generators and reheaters to provide 3500-psia 1000 F/l000 F steam for a conventional turbine generator.
The conceptual design was based on use of four reactors and the associated heat transfer systems in a socalled modular arrangement to supply steam to a single turbine-generator. This made it practical to consider replacement of an entire reactor vessel assembly after the core graphite received its allowable exposure to neutrons. The total fluence at which it was thought that additional graphite dimensional changes would become excessive was taken as 3 x neutrons/cm2 (E > 50 kev), or about eight years of full-power operation.
All portions of the systems in contact with the fluoride or fluoroborate salts would be fabricated of Hastelloy N that has a small amount of titanium added to improve the resistance to radiation damage. The graphite would be a specially coated grade having low gas permeability to xenon and better resistance to radiation damage than conventional material. The two-fluid concept involves joining graphite core elements to Hastelloy N tubing using a brazing process developed at ORNL.
The reactors and associated systems would be housed in concrete cells to provide biological shielding and double containment of all radioactive materials. Plant flowsheets and layouts were developed sufficiently during the study to give an indication of feasibility and to give a basis for cost estimates, but no optimization studies were made. Safety aspects were considered throughout the design effort, but no formal safety analysis was completed.
Fuel and blanket salts would be continuously processed in a nearby cell to remove fission products and to recover the bred product. The processing rate would correspond to removal of uranium and protactinium from the blanket on a 3-day cycle and rareearth fission products from the core on a 6-y cycle. Since no conceptual designs for the chemical plant were completed, cost estimates could not be on a definitive basis. The tentatively estimated fuel cycle cost is about 0.5 mill/kwhr, which includes the fixed charges and operating costs for the processing equipment, the fuel inventory charge, and the credit for bred fuel. Graphite replacement costs, which are not included, would add about 0.2 mill/kWhr.
The tentatively estimated total construction cost of a 1ooo-Mw(e) MSBR station, based on the early 1968 value of the dollar, is about $141 per kilowatt. The power production cost for a privately owned station, based on fixed charges of 13.7% and 80% plant factor, is about 4 mills/kwhr. The net thermal efficiency of the plant would be about 44.9%. The off-gas, fuel processing, afterheat removal, and maintenance systems needed further investigation at the time the study was suspended, and the limited performance of the graphite undoubtedly restricts the design and imposes a maintenance penalty, but the study did not disclose
any aspects which indicated that major technological discoveries would be required to design a two- fluid molten-salt reactor power statiohThe major concern was whether mechanical failure of graphite tubes in the reactor core would cause the effective lifetime of the core to be significantly less than the eight years imposed by the effects of irradiation on the graphite.
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