Integral experiments for fusion-reactor shield design. Summary of progress

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:6204021

Santoro, R T; Alsmiller, Jr, R G; Barnes, J M; Chapman, G T

Neutron and gamma-ray energy spectra from the reactions of approx. 14-MeV neutrons in blanket and shield materials and from the streaming of these neutrons through a cylindrical duct (L/D approx. 2) have been measured and calculated. These data are being obtained in a series of integral experiments to verify the radiation transport methods and nuclear data that are being used in nuclear design calculations for fusion reactors. The experimental procedures and analytical methods used to obtain the calculated data are reviewed. Comparisons between measured and calculated data for the experiments that have been performed to date are summarized.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6204021
• Report Number(s): CONF-830538-11; ON: DE83012601
• Resource Relation: Conference: 6. international conference on radiation shielding, Tokyo, Japan, 16 May 1983; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
SHIELDING
DESIGN
THERMONUCLEAR REACTORS
BREEDING BLANKETS
ENERGY SPECTRA
GAMMA RADIATION
NEUTRONS
RADIATION STREAMING
BARYONS
ELECTROMAGNETIC RADIATION
ELEMENTARY PARTICLES
FERMIONS
HADRONS
IONIZING RADIATIONS
NUCLEONS
RADIATIONS
REACTOR COMPONENTS
SPECTRA
700209* - Fusion Power Plant Technology- Component Development & Materials Testing