Reliability, availability, and quality assurance considerations for fusion components

Buende, R.

doi:10.1016/0920-3796(95)80032-s

Cited by 15 publications

(6 citation statements)

References 24 publications

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“…But some studies (e.g. [3,11,[103][104][105][106][107][108][109]) investigated the issue in sufficient depth to allow quantifying goals and issues. Table 4 shows the results of combining the methods and analysis of references [103,3].…”

Section: Reliability/availability/maintainability/inspectability (Rami)mentioning

confidence: 99%

Blanket/first wall challenges and required R&D on the pathway to DEMO

Abdou

Morley

Smolentsev

et al. 2015

Fusion Engineering and Design

276

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a b s t r a c tThe breeding blanket with integrated first wall (FW) is the key nuclear component for power extraction, tritium fuel sustainability, and radiation shielding in fusion reactors. The ITER device will address plasma burn physics and plasma support technology, but it does not have a breeding blanket. Current activities to develop "roadmaps" for realizing fusion power recognize the blanket/FW as one of the principal remaining challenges. Therefore, a central element of the current planning activities is focused on the question: what are the research and major facilities required to develop the blanket/FW to a level which enables the design, construction and successful operation of a fusion DEMO? The principal challenges in the development of the blanket/FW are: (1) the Fusion Nuclear Environment -a multiple-field environment (neutrons, heat/particle fluxes, magnetic field, etc.) with high magnitudes and steep gradients and transients; (2) Nuclear Heating in a large volume with sharp gradients -the nuclear heating drives most blanket phenomena, but accurate simulation of this nuclear heating can be done only in a DT-plasma based facility; and (3) Complex Configuration with blanket/first wall/divertor inside the vacuum vessel -the consequence is low fault tolerance and long repair/replacement time.These blanket/FW development challenges result in critical consequences: (a) non-fusion facilities (laboratory experiments) need to be substantial to simulate multiple fields/multiple effects and must be accompanied by extensive modeling; (b) results from non-fusion facilities will be limited and will not fully resolve key technical issues. A DT-plasma based fusion nuclear science facility (FNSF) is required to perform "multiple effects" and "integrated" experiments in the fusion nuclear environment; and (c) the Reliability/Availability/Maintainability/Inspectability (RAMI) of fusion nuclear components is a major challenge and is one of the primary reasons why the blanket/FW will pace fusion development toward a DEMO.This paper summarizes the top technical issues and elucidates the primary challenges in developing the blanket/first wall and identifies the key R&D needs in non-fusion and fusion facilities on the path to DEMO.Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (http:// creativecommons.org/licenses/by-nc-nd/4.0/).

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Section: Reliability/availability/maintainability/inspectability (Rami)mentioning

confidence: 99%

Blanket/first wall challenges and required R&D on the pathway to DEMO

Abdou

Morley

Smolentsev

et al. 2015

Fusion Engineering and Design

276

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“…Availability studies for the next generation devices have been performed since the first years of their conception. A first approximation is to target Fusion reactors to the same inherent availability level of a Fission reactor (70% to 80%) [2]. A recent RAMI study for ITER starts from 60% [3].…”

Section: Introductionmentioning

confidence: 99%

Development of high-availability ATCA/PCIe data acquisition instrumentation

Correia

Sousa

Batista

et al. 2015

2015 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and Their Applications (ANIMMA

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Latest Fusion energy experiments envision a quasicontinuous operation regime. In consequence, the largest experimental devices, currently in development, specify highavailability (HA) requirements for the whole plant infrastructure. HA features enable the whole facility to perform seamlessly in the case of failure of any of its components, coping with the increasing duration of plasma discharges (steady-state) and assuring safety of equipment, people, environment and investment. IPFN developed a control and data acquisition system, aiming for fast control of advanced Fusion devices, which is thus required to provide such HA features. The system is based on in-house developed Advanced Telecommunication Computing Architecture (ATCA) instrumentation modules -IO blades and data switch blades, establishing a PCIe network on the ATCA shelf's backplane. The data switch communicates to an external host computer through a PCIe data network. At the hardware management level, the system architecture takes advantage of ATCA native redundancy and "hot swap specifications to implement fail-over substitution of IO or data switch blades. A redundant host scheme is also supported by the ATCA/PCIe platform. At the software level, PCIe provides implementation of hot plug services, which translate the hardware changes to the corresponding software/operating system devices. The paper presents how the ATCA and PCIe based system can be setup to perform with the desired degree of HA, thus being suitable for advanced Fusion control and data acquisition systems.

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“…For DFLL-TBM in ITER with cyclic operation procedure, its constituents are structural components. PFM can become an important tool in reliability evaluation of structural components [3][4][5][6][7][8][9][10].…”

Section: Introductionmentioning

confidence: 99%

“…However, reliability data of a blanket component cannot be directly derived because it only exists in the fusion tokamak reactors with complicated structure. To assess the reliability of a blanket component, fault trees were used in literatures [3]. The failure rates of the constituents under different conditions of application were derived from basic failure rates, which were valid for a certain set of reference conditions by scaling up or down according to deviations from that set of conditions.…”

Section: Introductionmentioning

confidence: 99%