Published 1995 | Version v1
Miscellaneous Open

The production, characterization, and neutronic performance of boron nitride coated uranium dioxide fuel

  • 1. Turkish Atomic Energy Authority, Nuclear Computing and Design Group, Ankara (Turkey)
  • 2. Hacettepe Univ., Nuclear Engineering Dept., Ankara (Turkey)
  • 3. Kimya Muhendisligi Bolumu, Orta Dogu Teknik Univ., Ankara (Turkey)

Description

The fuel pellets produced by sol-gel technique were coated with boron nitride (BN). This was achieved through chemical vapor deposition (CVD) using boron trichloride and ammonia. Mixing and chemical reaction take place at a temperature around 875 K. The coated samples were then sintered at 1600 K. Thermal reactor physics lattice-cell code WIMS-D/4 was used in the neutronic analysis of CANDU fuel bundle to observe the neutronic performance of the coated fuel. Three types of fuel were considered; fuel made of natural uranium, slightly enriched uranium (SEU, enrichment: 0.82 % U-235), and SEU with various BN coatings. The burnup calculations showed that feasible coating thickness is between 1 to 2 μm. (author)

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Part of:
Conference proceedings of the 4. international conference on CANDU fuel. V. 1,2

Additional details

Publishing Information

ISBN
0-919784-53-4
Imprint Title
Conference proceedings of the 4. international conference on CANDU fuel. V. 1,2
Imprint Pagination
830 p.
Journal Page Range
v. 1 [10 p.]
Report number
INIS-CA--0069(v.1,2)

Conference

Title
safe, reliable, economical
Acronym
CANDU fuel
Dates
1-4 Oct 1995
Place
Pembroke, ON (Canada)

Optional Information

Notes
21 refs., 9 figs.