Published 1992 | Version v1
Book

DIII-D radiation shielding procedures and experiences

Creators

  • 1. General Atomic Co., San Diego, CA (United States)

Description

This paper reports on the DIII-D tokamak which operates with a neutron radiation shield to allow enhanced plasma operations with increased neutron production while minimizing the site boundary dose level. Neutron rates as high as 4 x 1015 neutrons/s and total neutron production as high as 4 x 1015 neutrons per shot are obtained while maintaining the site does below the DOE administrative level of 20 mrem per year; a much more restrictive level than the State of California radiation limits. The radiation shielding has increased by a factor of 300 over the preshield value and is in agreement with the design calculation. The maximum site neutron dose since installation of the shield has been less than 0.03 mrem for a shot and less than 0.4 mrem for a day. The site neutron and gamma dose are monitored continuously during operations by a PC-based computer system that provides the means of measuring the low dose levels that occur during a shot by including postshot background subtraction

Additional details

Publishing Information

Publisher
IEEE Service Center.
Imprint Place
Piscataway, NJ (UNITED STATES)
ISBN
0-7803-0132-3
Imprint Title
Proceedings of fusion engineering
Imprint Pagination
1236 p.
Journal Page Range
p. 617-620.

Conference

Title
14. IEEE symposium on fusion engineering.
Dates
30 Sep - 3 Oct 1991.
Place
San Diego, CA (United States).

Optional Information

Secondary number(s)
CONF-910968--.