Neutron streaming analysis in the fusion ignition experiment IGNITEX

Author

Parish ; Shofolu, B. ; Booth ; Carrera ; Hertel

fYear

1990

fDate

21-23 May 1990

Firstpage

95

Abstract

Summary form only given. The effect of neutron streaming in the out-vessel maintenance inside of the primary shielding in IGNITEX has been analyzed by means of Monte Carlo techniques. The transport of neutrons and photons through diagnostic and vacuum penetrations during the IGNITEX pulse was simulated with the 3-D, MCNP numerical code. Various types of penetrations were considered, including maintenance ports (horizontal outboard access), horizontal diagnostic ports (horizontal outboard sight), and vertical diagnostic ports (vertical top/bottom sight). Shielding and design modifications for access piping to the IGNITEX machine were established on the basis of a multidimensional radiation analysis

Keywords

Monte Carlo methods; fusion reactor theory and design; IGNITEX; MCNP numerical code; Monte Carlo techniques; access piping; diagnostic ports; fusion ignition experiment; horizontal outboard access; maintenance ports; multidimensional radiation analysis; neutron streaming analysis; out-vessel maintenance; outboard sight; primary shielding; simulation; vacuum penetrations; vertical top/bottom sight;

fLanguage

English

Publisher

ieee

Conference_Titel

Plasma Science, 1990. IEEE Conference Record - Abstracts., 1990 IEEE International Conference on

Conference_Location

Oakland, CA, USA

Type

conf

DOI

10.1109/PLASMA.1990.110535

Filename

5725812