Nuclear modules of ITER tokamak systems code

Conference · Thu Oct 01 04:00:00 EDT 1987

OSTI ID:5829909

Gohar, Y; Baker, C; Brooks, J; Finn, P; Hassanein, A; Willms, S; Barr, W; Bushigin, A; Kalyanam, K M; Haines, J

Nuclear modules were developed to model various reactor components in the ITER systems code. Several design options and cost algorithms are included for each component. The first wall, blanket and shield modules calculate the beryllium zone thickness, the disruptions results, the nuclear responses in different components including the toroidal field coils. Tungsten shield/water coolant/steel structure and steel shield/water coolant are the shield options for the inboard and outboard sections of the reactor. Lithium nitrate dissolved in the water coolant with a variable beryllium zone thickness in the outboard section of the reactor provides the tritium breeding capability. The reactor vault module defines the thickness of the reactor wall and the roof based on the dose equivalent during operation including skyshine contribution. The impurity control module provides the design parameters for the divertor including plate design, heat load, erosion rate, tritium permeation through the plate material to the coolant, plasma contamination by sputtered impurities, and plate lifetime. Several materials: Be, C, V, Mo, and W can be used for the divertor plate to cover a range of plasma edge temperatures. The tritium module calculates tritium and deuterium flow rates for the reactor plant. The tritium inventory in the fuelers, neutral beams, vacuum pumps, impurity control, first wall, and blanket is calculated. Tritium requirements are provided for different operating conditions. The nuclear models are summarized in this paper including the different design options and key analyses of each module. 39 refs., 3 tabs.

• Research Organization: Argonne National Lab., IL (USA); Los Alamos National Lab., NM (USA); Lawrence Livermore National Lab., CA (USA); Ontario Hydro, Mississauga (Canada); Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5829909
• Report Number(s): CONF-871007-68; ON: DE88002884
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALGORITHMS
BOUNDARY LAYERS
BREEDING BLANKETS
CAPITALIZED COST
COMPUTER CODES
CONTROL SYSTEMS
COST
DESIGN
DIVERTORS
FIRST WALL
HYDROGEN ISOTOPES
IMPURITIES
ISOTOPES
LAYERS
MATHEMATICAL LOGIC
NEUTRON FLUENCE
PLASMA DISRUPTION
PLASMA SCRAPE-OFF LAYER
POWER DENSITY
REACTOR COMPONENTS
SHIELDING
SUPERCONDUCTING COILS
SYSTEMS ANALYSIS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
WALL LOADING