Accession Number:

AD0754767

Title:

Multigroup Analysis of Neutron and Secondary Gamma Ray Transport in Concrete.

Descriptive Note:

Final rept. 1 Jan 70-15 May 71,

Corporate Author:

SCIENCE APPLICATIONS INC LA JOLLA CALIF

Report Date:

1972-10-01

Pagination or Media Count:

205.0

Abstract:

Several calculations were compared with a Gulf General Atomic concrete experiment to evaluate multigroup calculational techniques of neutron and secondary gamma transport on concrete, including the effects of cross sections. Discrete ordinates calculations were performed with the DTF, DOT, and TDA codes. These results were compared with the experiment and with two-dimensional, time-dependent Monte Carlo calculations with MORSE, including effects of lead shielding around the NE 213 detector. The concrete composition included oxygen, hydrogen, calcium, and silicon for transport, plus trace amounts of potassium, aluminum, and iron for gamma production. Author

Subject Categories:

  • Guided Missile Launching and Basing Support
  • Nuclear Radiation Shielding, Protection and Safety
  • Radioactivity, Radioactive Wastes and Fission Products

Distribution Statement:

APPROVED FOR PUBLIC RELEASE