Published September 2003 | Version v1
Journal article Metadata-only

Comprehensive activation calculations of reference materials for near term reactor concepts

Creators

Description

Neutron transport calculations using MCNP and activation calculations using FISPACT have been carried out to produce a comprehensive dataset to be used in the assessment of materials for fusion power plants. Examples are given to illustrate the useful application of pathway analysis, importance diagrams and the effects of impurities on activation and dose

Additional details

Identifiers

DOI
10.1016/S0920-3796(03)00106-6;
arXiv
arXiv:hep-th/9901010v1;
PII
S0920379603001066;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
69
Journal Issue
1-4
Journal Page Range
p. 711-717
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
22. symposium on fusion technology
Dates
9-13 Sep 2002
Place
Helsinki (Finland)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35045779
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
IMPURITIES; MONTE CARLO METHOD; NEUTRON TRANSPORT; RADIOACTIVATION; THERMONUCLEAR REACTOR MATERIALS
Descriptors DEC
CALCULATION METHODS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT

Optional Information

Copyright
Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.