Published January 1994
| Version v1
Miscellaneous
Shielding for future fusion reactors
Creators
- 1. Reactor and Neutron Physics Dept., Nuclear Research Centre, A.E.A., Cairo (Egypt)
Description
This paper outlines the main principles of shield design criteria for the future fusion reactors with an emphasis on the main parameters for shield optimization. The nuclear performance of the blanket and the inboard, outboard and penetration shields and their significant impact on the performance, operating conditions and cost of the fusion reactors are also discussed. In addition, the measured and calculated data of 14 MeV neutron fluxes and energy distributions in materials widely used for shield construction of fusion reactors are given and discussed. (orig.)
Additional details
Publishing Information
- ISBN
- 3-89336-130-8
- Imprint Title
- Third workshop on plasma and laser physics. Lecture notes
- Imprint Pagination
- 378 p.
- Journal Volume
- 15
- Series
- Bilateral Seminars of the International Bureau.
- Journal Page Range
- p. 177-202.
Conference
- Title
- 3. workshop on plasma and laser physics.
- Dates
- 3-7 Oct 1993.
- Place
- Ismailia (Egypt).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 26004084
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BREEDING BLANKETS; COST; DESIGN; FAST NEUTRONS; LECTURES; MEV RANGE 10-100; NEUTRON FLUX; NEUTRON SPECTRA; OPTIMIZATION; PHYSICAL RADIATION EFFECTS; PLASMA; REACTORS; SHIELDING; SHIELDING MATERIALS; SHIELDS; STEELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR MATERIALS
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; DOCUMENT TYPES; ELEMENTARY PARTICLES; ENERGY RANGE; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MEV RANGE; NEUTRONS; NUCLEONS; RADIATION EFFECTS; RADIATION FLUX; SPECTRA