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Articles

On-Board Dose Measurement and its Monte Carlo Analysis in a Low Level Waste Shipping Vessel

Pages 309-316 | Published online: 19 Jul 2013

REFERENCES

  • Briesmeister, J. F. (Ed.) MCNP — A General Monte Carlo N-Particle Transport Code. LA-12625-M (March 1997).
  • Ueki, K., Namito, Y. and Fuse, T. Measurement of Dose Rates and Monte Carlo Analysis of Neutrons in a Spent-fuel Shipping Vessel. Nucl. Technol. 74, 164–175 (August 1986).
  • Malenfant, R. E. QAD: A Series of Point-Kernel General Purpose Shielding Programs. LA-3572 (April 1967).
  • Engle Jr, W. W. A Users Manual for ANISN, A One Dimensional Discrete Ordinates Transport Code With Anisotropic Scattering. K-1963 (Union Carbide Corp.) (1967).
  • Rhodes, W. A. and Mynatt, F. R. The DOT-III Two-Dimensional Discrete Ordinate Transport Code. ORNL-TM-4280 (1973).
  • ICRP . Data for Use in Protection against External Radiation. Publication 51, Ann. ICRP 17 (2–3) (Oxford: Pergamon) (1987).

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