Plutonium nitride

Pnictides. Plutonium nitride, PuN, has been studied as a possible fast-reactor fuel. It can be prepared by reaction of PuH with NH at 600—650°C or N2 above 230°C. The pnictides ate also interesting for their soHd-state magnetic and electrical properties. For the latter reason they also have been prepared as single crystals (165). 

Uranium and mixed uranium—plutonium nitrides have a potential use as nuclear fuels for lead cooled fast reactors (136—139). Reactors of this type have been proposed for use ia deep-sea research vehicles (136). However, similar to the oxides, ia order for these materials to be useful as fuels, the nitrides must have an appropriate size and shape, ie, spheres. Microspheres of uranium nitrides have been fabricated by internal gelation and carbothermic reduction (140,141). Another use for uranium nitrides is as a catalyst for the cracking of NH at 550°C, which results ia high yields of H2 (142). 

The reaction of plutonium metal with N2 in a sputtering device 41) resulted in the observation of matrix-isolated, plutonium nitride species. The species observed were PuN and PUN2, the latter being a linear species. 

Plutonium nitride, 19 691 Plutonium oxalates, 19 691 Plutonium(IV) oxide, 19 669 Plutonium oxides, 19 688-689 Plutonium oxyhalides, 19 689-690 Plutonium pnictides, 19 691 Plutonium-producing reactors, storage of radioactive waste from, 25 855 Plutonium radioisotopes, 21 319 Plutonium refractory compounds, 19 687 Plutonium reprocessing plants, 19 686 Plutonium silicides, 19 690-691 Plutonium solutions, self-radiolysis of, 19 694... 

Mercury(II) /V-pcrchlory lbcnzylamidc. 3651 Monopotassium perchlorylamide, 3994 Nitrogen triiodide-silver amide, 4634 Nitrosylruthenium trichloride, 4144 Pentaamminedinitrogenruthenium(II) salts, 4596 Pentakis(dimethylamino)tantalum, 3384 Pentasilver diamidophosphate, 0046 Pentasilver orthodiamidophosphate, 0044 Plutonium nitride, 4726 Poly (dimercury immonium hydroxide), 4422... 

Platinum tetrafluoride, 4342 Plutonium bismuthide, 0231 Plutonium hexafluoride, 4366 Plutonium(III) hydride, 4504 Plutonium(IV) nitrate, 4763a Plutonium nitride, 4721 Plutonium, 4882 Poly(acetylene), 0683 Poly(acrylonitrile), 1105... 

Actinide nitrides are known for Th through Cm. All of the nitrides are high melting compounds with melting points of 2630 °C, 2560 °C, and 2580 °C for Th, Np, and Pu, respectively. The actinide nitrides can decompose to give N2. Thorium, uranimn, and plutonium nitrides are well known and can be used as nuclear fiiels. Fuels of this type, especially uranium and mixed uranium plutonium nitrides, can be used in lead-cooled fast reactors, which have been proposed as a possible next-generation nuclear reactor and for use in deep-sea research vehicles. 

Plutonium oxide, PuO (CAS 12035-83-5) Plutonium dioxide, PuOi (CAS 12059-95-9) Plutonium nitride, PuN (CAS 12033-54-4) Plutonium tetrafluoride, Pup4 (CAS 13709-56-3) Plutonium hexafluoride, PuF6 (CAS 13693-06-6)... 

Plutonium nitride. Unlike the corresponding uranium-nitrogen system, only the one plutonium nitride PuN exists. It is prepared by heating plutonium hydride in nitrogen at 250 to 400 C, by reacting plutonium metal with a hydrogen-ammonia mixture at 600°C, or by direction reaction of molten plutonium with nitrogen at 1000 C. Plutonium nitride forms solid solutions with UN. However, because of the appreciable volatility and dissociation of PuN at temperatures at about 1600 C and above, the ternary (U, Pu)N is less attractive as a nuclear fuel than pure UN [K2, S4]. 

Although some of these saltlike nitrides have high melting points (for instance, thorium nitride 2820"C uranium nitride 2800°C plutonium nitride 2550 beryllium nitride 2200 C barium nitride 2200"C), they are sensitive to hydrolysis and react readily with water or moisture to give ammonia and the corresponding metal oxide or hydroxide. Consequently, they do not meet the refractory requirements as interpreted here. Some of these nitrides are useful industrial materials particularly as sintering additives for the production of silicon nitride, aluminum nitride, and cubic boron nitride (see Ch. 14). 

For mixed uranium-plutonium fuel - MOX fuel with weapon-grade plutonium (MOX-W) MOX fuel with reactor-grade plutonium (MOX-R), either extracted in chemical reprocessing of LWR spent fuel or self-generated TRUOX fuel (MOX fuel with the addition of minor actinides extracted from LWR spent fuel) and mixed uranium-plutonium nitride fuel. 

One of the principal criteria for fuel with an inert matrix is its reproces g ability. From this point of view solid solutions of plutonium carbides, plutonium nitrides and inert matrices ZrC and ZrN seem to be the best candidates. 

Fuel type Cylindrical container-type fuel rods with fuel pellets of mixed uranium-plutonium nitride fuel of 13.3 g/cm density steel claddings... 

The fourth type of fuel assembly is used in the lateral blanket. Mixed uranium-plutonium nitride fuel with a density of 13.3 g/cm and plutonium content of 13.7 % is used in all core zones. Axial and lateral blankets contain pellets of depleted uranium nitride with a density of 13.3 g/cm (Table XXIII-7). 

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