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Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
T. Eich, A. Werner
Fusion Science and Technology | Volume 53 | Number 3 | April 2008 | Pages 761-779
Technical Paper | doi.org/10.13182/FST08-A1733
Articles are hosted by Taylor and Francis Online.
The heat load due to plasma radiation is estimated for the plasma wall components of the stellarator Wendelstein 7-X (W7-X). A fully three-dimensional Monte Carlo code is used to simulate heating of first-wall components due to photon emission from the plasma. The plasma wall components can be described in a complex way with arbitrary shapes and orientation and flexible numerical representation. The volume radiation distribution is assumed to be described by poloidal symmetric and radially varying one-dimensional profiles aligned to the magnetic flux surfaces. A further example is given by a nonpoloidal symmetric radiation distribution following the five X point regions of the island divertor magnetic structure. Several realistic and artificial radiation profiles are chosen to investigate the local heat loads on an idealized plasma wall. The first detailed technical application of the code is the estimation of the local heat load on the Thomson scattering windows and on the inner surface of several vacuum ports of one half-module of the W7-X plasma vessel.