Radiation shielding for fusion reactors
Description
Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel. (author)
Availability note (English)
Available from the Internet at URL https://doi.org/10.1080/00223131.2000.10874838Additional details
Identifiers
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of ninth international conference on radiation shielding
- Imprint Pagination
- 906 p.
- Journal Page Range
- p. 11-18
Conference
- Title
- 9. international conference on radiation shielding
- Acronym
- ICRS-9
- Dates
- 17-22 Oct 1999
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51054545
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DOSE RATES; ITER TOKAMAK; ONE-DIMENSIONAL CALCULATIONS; OPENINGS; OPTIMIZATION; PARAMETRIC ANALYSIS; RADIATION STREAMING; RADIATION TRANSPORT; SHIELDING; SHIELDS; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- 1 ref., 10 figs., 10 tabs.; This record replaces 32000935 Imprint:Published in Journal of Nuclear Science and Technology, Suppl. 1