journal article·2016-12

A comparative study of nitride purity and Am fabrication losses in PuN materials by the powder and internal gelation production routes

Marcus Hedberg, Christian Ekberg

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Abstract

Fabrication of plutonium containing fuels through the internal gelation method has mostly been studied in mixed metal systems such as U, Pu or Zr, Pu. In this work production of undiluted PuN has been performed by carbothermal reduction on both oxide powder and Pu microspheres produced by the internal gelation method. Nitride purities reached using the different methods have been studied together with final densities achieved during pellet fabrication as well as losses of ingrown Am during the different production steps. Formation of Pu microspheres was successfully performed using the internal gelation method, although extensive microsphere fracturing occurred during thermal treatment. Final densities of PuN pellets produced by cold pressing and sintering reached 70-80% of theoretical density. Am losses during the carbothermal reduction step was on average about 3.7%. After sintering about 11% of Am was lost in total through the entire production process if sintering in N-2 + 5% H-2 atmosphere while about 50% of the Am in total was lost when using Ar as sintering atmosphere.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear materials and radiation effects

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References (30)

Show source-provided references
1. Ledergerber · 1996
2. Zirconium nitride as inert matrix for fast systems10.1016/S0022-3115(03)00133-8 ↗
3. Mononitride fuels for fast reactors10.1023/B:ATEN.0000007886.86817.32 ↗
4. Some aspects of the use of ZrN as an inert matrix for actinide fuels10.1016/S0022-3115(00)00722-4 ↗
5. Selection of materials as diluents for burning plutonium fuels in nuclear reactors10.1016/S0022-3115(99)00144-0 ↗
6. Status of sol-gel process for nuclear fuel10.1007/s10971-008-1725-0 ↗
7. Preparation and characterisation and out-of-pile property evaluation of (U, Pu)N fuel pellets10.1016/0022-3115(91)90391-J ↗
8. Sol-gel microsphere pelletisation process for fabrication of (U,Pu)O2, (U,Pu)C and (U,Pu)N fuel pellets for the prototype fast breeder reactor in India10.1007/BF02437192 ↗
9. Studies on plutonium-zirconium co-precipitation and carbothermal reduction in the internal gelation process for nitride fuel preparation10.1016/j.jnucmat.2016.07.055 ↗
10. Fabrication of uranium-plutonium oxide microspheres by the hydrolysis process10.1016/0022-3115(77)90079-4 ↗
11. Sol – gel microsphere pelletization: a powder – free advanced process for fabrication of ceramic nuclear fuel pellets10.1007/BF02757652 ↗
12. Kanij · 1974
13. Brugghen v.d · 1970
14. The basic chemistry involved in the internal-gelation method of precipitating uranium as determined by pH measurements10.1524/ract.1987.42.3.121 ↗
15. Treatment techniques to prevent cracking of amorphous microspheres made by internal gelation process10.1016/j.jnucmat.2010.08.007 ↗
16. Advanced fuel fabrication10.1016/0022-3115(89)90182-7 ↗
17. Kinetics of the carbothermic synthesis of uranium mononitride microspheres10.1016/0022-3115(91)90363-C ↗
18. Phase equilibria and thermodynamics of the Pu-O system: 1400 K to 1610 K *10.1016/0022-3115(87)90289-3 ↗
19. Thermodynamic modelling of the plutonium-oxygen system10.1016/j.jnucmat.2008.06.013 ↗
20. Mechanism and kinetics of the uranium-plutonium mononitride synthesis10.1016/0022-3115(92)90451-P ↗
21. Preparation of uranium nitride in the form of microspheres10.1016/0022-3115(92)90450-Y ↗
22. Thermochemical modelling of uranium-free nitride fuels10.1080/18811248.2004.9715508 ↗
23. Vaporization behaviour of (Pu,Am)N10.1016/0925-8388(95)01512-4 ↗
24. M. Takano, A. Itoh, M. Akabori, K. Minato, M. Numata, Study on The Stability of AmN and (Am,Zr)N, 2003, Global conference 2003, New Orleans, LA.
25. Matzke · 1986
26. ISO (International Organization for Standardization) · 2003
27. M. Hedberg, M. Streit, C. Ekberg, Effects of carbide impurities on the lattice parameter of mixed zirconium nitrides, submitted to Progress in Nuclear Engineering.
28. Arai · 2012
29. Removal of americium by its evaporation during carbothermic reduction of plutonium dioxide10.1080/18811248.1985.9735663 ↗
30. The vaporization behaviour of americium dioxide by use of mass spectrometry10.1016/j.jnucmat.2010.12.024 ↗