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Blanket fuel

The present work at Rocky Flats is an extension of the Argonne work and is directed to development of a proliferation resistant pyrochemical process for LMFBR fuels. This article describes a conceptual pyrochemical process and preliminary engineering concepts for coprocessing uranium and plutonium in spent LMFBR core-axial blanket and radial blanket fuels using the Salt Transport Process. [Pg.185]

The block flow diagram presented in Figure 2 gives the major operations of the conceptual process. Feed to the process is one core-axial blanket or radial blanket fuel assembly. The fuel assembly hardware below the active section is removed prior to processing. The hardware above the active section is not introduced into the process. In this low decontamination process, the active section of the spent fuel is selectively dissolved into molten metals and molten salts from which coprocessing of uranium and... [Pg.188]

Because both zinc and magnesium are volatile, these acceptor alloy elements are separated from the actinides by vacuum distillation. The zinc-magnesium overhead product from vacuum distillation is recycled. After the volatile solvent metals are removed, the resultant distillation bottom products (U-Pu for core fuel and U for blanket fuel) are converted to suitable oxides by reaction with oxygen. The oxide products are available for refabrication into new fuel. The FP-3 elements that follow plutonium and the... [Pg.190]

To determine the process size, material balances were calculated for each process operation. Feed to the process was one core-axial blanket fuel assembly. [Pg.191]

AI Reference Oxide LMFBR Core-Axial Blanket Fuel Assembly (21)... [Pg.191]

In the FBR fuel cycles, the fraction (i.e., 21% in the examples above) of the blanket fuel recycled for use in refabricating driver fuel after AIROX processing only depends on the concentration of fissile material in the Civex or Pyrocivex product. As the fissile content of the Civex or Pyrocivex product is decreased, the amount of blanket fuel recycled for driver fuel fabrication must also be decreased proportionately and the amount of spent blanket fuel processed by the Civex or Pyrocivex process must be increased. [Pg.217]

The reactor contains three different fuel-bearing regions core, axial blanket, and radial blanket. Fuel rods for the core and axial blanket consist of stainless steel tubing about in outside diameter, mounted vertically. The middle 4 ft of each tube is filled with core material, consisting of a mixture of 17 w/o PUO2 and 83 w/o UOj made from depleted uranium... [Pg.149]

X 10 n/(cm -s), and for the breeder parameters of Fig. 3.34, the estimated yearly production of C for a 1000-MWe fast breeder is estimated to be 3.3 Ci/year. Relatively little C is produced in the blanket fuel because of the lower neutron flux there. [Pg.398]

Tfie concentration of plutonium in combined core and blanket fuel from the LMFBR is more than 10 times that of LWR fuel. This is the most significant difference between the two fuels with respect to reprocessing. Other important differences are the greater amounts of tritium and the 140 percent greater ruthenium activity, and the 60 percent greater overall specific activity of ISO-day cooled LMFBR fuel. [Pg.528]

Besides highly radioactive wastes of the core and blankets (spent core and blanket fuel subassemblies), medium and low level radioactive wastes are produced in... [Pg.167]

Figure 2 shows the results of sample calculations utilizing the homogenized and two-region inhour equations. The examples are infinite slab reactors with uranium-233 as the core and uranium-235 as the blanket fuels. The choice of placing uranium-233 on the inside is because of a particular study under way at the time the calculations were made. Fuel concentrations... [Pg.264]

Upper blanket fuel pellet Core fuel pellet... [Pg.2692]

Lower blanket fuel pellet Wire spacer Lower plug... [Pg.2692]

Critical experiments utilizing U and Th fuels have been conducted at the Bettis Atomic Power laboratory since 1964. The critical assemblies were of the seed-and-blanket type and the experiments were performed In support of the Light-Water Breeder program. Two sets of experiments have been conducted to date. The first set consisted of l5-in, high assemblies which contained 26 wt% UO2- Zr02 seed fuel in which the uranium was either or "U, and blanket fuel of Th02 or 1 wt% UOa-ThOa. All elements were rod type with Zr clad. The second set consisted of 12 wt% UOa-ThOa seed fuel 28-in. high, and ThOa blanket fuel. Future experiments are planned in this second set with lower concentrations of in the seed fuel and with blanket fuel that contains... [Pg.190]

Blanket fuel pin dimensions and density of fertile column... [Pg.58]

Core fuel Blanket fuel Maximum, fuel (at start of life) Maximum, blanket (at end of life) Average core... [Pg.62]

A dissolver solution of irradiated fast neutron reactor mixed oxide (MOX) fuel in JAEA contains a number of TRU elements and FPs than in KfK Since U is used as blanket fuel and TRU elements are sup>posed to recover by other chemical process, it is need to remove TRU elements and FPs from UNH crystals in the U crystallization process. It would be also bring about reduction in the cost for the recovered U storage and the blanket fuel fabrication due to decreased radiation shielding. Therefore, the behavior of TRU elements and FPs in the U crystallization process must be confirmed experimentally. [Pg.384]

Since U is recovered as UNH crystal for a blanket fuel fabrication in the U crystallization process, the crystal ratio of U should be evaluated with a dissolver solution of irradiated fast neutron reactor. The crystal ratio of UNH affects HNO3 concentration in the feed... [Pg.384]

The 4S is a sodium-cooled reactor therefore, its neutron spectrum is fast. However, the 4S is not a breeder reactor since blanket fuel, usually consisting of depleted uranium located around the core to absorb leakage neutrons from the core to achieve breeding of fissile materials, is not provided in its basic design. [Pg.396]

To ensure a 30-year period of core operation without refuelling, the plan is to replace CPS rods, as their 10-year lifetime expires, for redundant rods located in cells of the radial blanket. The reactivity balance in refuelling of the core and blanket fuel assemblies is given in Table XVI-8. [Pg.463]

Refueling is to be done every six months or so, with about one-fifth of the core and blanket fuel assemblies exchanged each cycle. [Pg.121]

The core includes fuel assemblies with MOX fuel (Fig. XXI-5), fuel assemblies of the internal blanket, fuel assemblies of the side blanket, shielding assemblies containing natural boron carbide, and cells for in-reactor storage. Design characteristics of the BMN-170 core and fuel assemblies are presented in Table XXI-2. [Pg.593]


See other pages where Blanket fuel is mentioned: [Pg.214]    [Pg.221]    [Pg.222]    [Pg.368]    [Pg.181]    [Pg.217]    [Pg.217]    [Pg.201]    [Pg.145]    [Pg.166]    [Pg.2691]    [Pg.2828]    [Pg.2830]    [Pg.1]    [Pg.58]    [Pg.64]    [Pg.65]    [Pg.454]    [Pg.702]    [Pg.837]    [Pg.15]    [Pg.553]    [Pg.611]    [Pg.131]   
See also in sourсe #XX -- [ Pg.100 , Pg.103 ]




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Blanket fuel pin dimensions and density of fertile column

Blanketing

Core, axial blanket fuel assembly

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