Published 1983 | Version v1
Book

The impact of key design parameters on neutron wall load in an ignited tokamak

Creators

  • 1. Fusion Engineering Design Center/Grumman Aerospace Corporation, Oak Ridge National Laboratory, Oak Ridge, TN

Description

A study was performed to determine the impact of key design parameters on neutron wall load in an ignited deuterium-tritium (D-T) tokamak. Systems effects of parameter variations were determined using the Fusion Engineering Design Center (FEDC) Systems Code. Poloidal variations in neutron wall load were determined using the Monte Carlo Code for Neutron and Photon Transport (MCNP). The marked impact of key design parameters is quantitatively shown

Additional details

Publishing Information

Publisher
I.E.E.E.
Imprint Place
New York, NY (USA)
Imprint Title
Fusion engineering. Vol. 2
Journal Page Range
p. 1878-1882.

Conference

Title
10. symposium on fusion engineering.
Dates
5-9 Dec 1983.
Place
Philadelphia, PA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
16028427
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMBUSTION; COMPUTER CODES; D-T REACTORS; F CODES; M CODES; MONTE CARLO METHOD; NEUTRON TRANSPORT; NEUTRONS; SPECIFICATIONS; WALL LOADING
Descriptors DEC
BARYONS; CHEMICAL REACTIONS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; OXIDATION; POWER DENSITY; RADIATION TRANSPORT; THERMONUCLEAR REACTORS