Page 405 - Fundamentals of Magnetic Thermonuclear Reactor Design

Mechanics of Magnetic Fusion Reactors Chapter | 12 383

The coil conductor was shown to be subject to two types of cyclic loads.
Coil charge and discharge lead to its longitudinal 0.12% deformation range. In
addition, ponderomotive forces acting on the TFC during a working cycle cause
a 0.04% cyclic deformation. A static deformation in the absence of electro-
magnetic forces mostly depends on the conductor jacket material, that is, on its
temperature-induced shrinkage due to cooling from the fabrication temperature
of ∼650 K to the operating temperature of ∼4 K.
Tests included a thousand variable range (0.04% and 0.12%) loading cycles
and validated both the toroidal field conductor insert compliance with design
parameters and the stability of the superconducting cable’s electrical–physical
characteristics.

APPENDIX A.12.4 CODES AND STANDARDS FOR TOKAMAKS

In the course of designing a fusion reactor, it is necessary to ensure that the
reactor’s key parameters, such as power, size and tritium mass, are in com-
pliance with local safety regulations. In many countries, including France,
where ITER is being constructed, regulatory authorities set equipment qual-
ity and safety requirements explicitly and make them legally and technically
binding.
In the case of fission reactors, these requirements are harmonised with nu-
clear codes and standards developed based on the many years of experience in
developing and running nuclear reactors and used to design concrete systems
and structures. Thermonuclear unified codes and standards are yet to be devel-
oped. In the interim, fusion-specific design standards for assessing the mechani-
cal strength of superconducting MS [13] and in-vessel components have been
developed to apply for ITER.
C&S for ITER components are based on a comprehensive analysis of
safety requirements. For example, some components may fall under codes
and standards for nuclear systems containing a fluid under pressure (pressure
systems).
The principal safety requirement applicable to equipment fulfilling a con-
finement function is structural integrity and leak tightness. The design of such
equipment should take into account the entire static and cyclic loading profile of
a structure, including the coolant pressure, electromagnetic forces and seismic
effects. Seismic resistivity is analysed with due regard to the combined effect of
operational and seismic stresses.
Design C&S adopted for ITER may be divided into two groups: ITER-specific
C&S and existing industrial C&S [14].
Existing industrial C&S include the following:
l ASME codes
l ASME/ANSI piping, pump and valve C&S
l RCC-MR 2007 and RCC-MRx 2013
l EU harmonised standards