Published October 16, 2018 | Version v1
Report

Overview of the NSTX-U Recovery Project Physics and Engineering Design

  • 1. Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ 08540 (United States)

Description

Full text: The NSTX-U device began operation in 2016, producing 10 weeks of commissioning and scientific operations. However, a number of technical issues, including the failure of a key divertor coil, resulted in the suspension of operations. A comprehensive extent of condition review was initiated at the request of the Department of Energy; this paper will summarize the result of that process, focussing on the design and implementation improvements that are in progress in order to resume operation and increase reliability. Many elements of the physics design have been revisited as part of the recovery, although most key NSTX-U mission goals remain. New requirements for the divertor heat fluxes have been defined, based on recent SOL heat flux width models. New halo currents loads have been determined based on combining data from NSTX, NSTX-U, MAST, and conventional aspect ratio devices. New error field analysis has been conducted, with the goal of optimizing both the global MHD stability and minimizing PFC heat flux asymmetries for scenarios with large poloidal flux expansion. New divertor coil current requirements have been defined, based on the tolerable heat fluxes and current drive for the various potential equilibria. Numerous design improvements are being included as part of the recovery effort, with a primary goal of supporting flexible operations at Bt = 1 T, Ip = 2 MA, Pinj = 10 MW, and tpulse = 5 s. New designs of graphite plasma-facing components utilize castellations to reduce the mechanical stresses, allowing tiles to reach surface temperature limits, ∼ 1600°C, driven by sublimation. Improved divertor coil designs simplify fabrication and facilitate turn-to-turn testing. Modifications to the NSTX-U vacuum chamber will eliminate one the ceramic insulators necessary for coaxial helicity injection (CHI), increasing system reliability at the expense of the CHI research capability. The physics and engineering R&D activities that support recovery will be summarized, along with highlights of the new design. Work supported by the U.S. Department of Energy Contract DE-AC02-09CH11466 and DE-AC05-00OR22725. (author)

Part of:
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
844 p.
Journal Page Range
p. 695
Report number
IAEA-CN--258

Conference

Title
27. IAEA Fusion Energy Conference
Acronym
FEC 2018
Dates
22-27 Oct 2018
Place
Ahmedabad (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50057780
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMMISSIONING; GRAPHITE; HEAT FLUX; MAGNETOHYDRODYNAMICS; NSTX DEVICE; OPTIMIZATION
Descriptors DEC
CARBON; CLOSED PLASMA DEVICES; ELEMENTS; FLUID MECHANICS; HYDRODYNAMICS; MECHANICS; MINERALS; NONMETALS; SPHEROMAK DEVICES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Contract/Grant/Project number
Contract DE-AC02-09CH11466; DE-AC05-00OR22725
Secondary number(s)
IAEA-CN--258-733