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Title: TPX remote maintenance and shielding

Abstract

The Tokamak Physics Experiment machine design incorporates comprehensive planning for efficient and safe component maintenance. Three programmatic decisions have been made to insure the successful implementation of this objective. First, the tokamak incorporates radiation shielding to reduce activation of components and limit the dose rate to personnel working on the outside of the machine. This allows most of the ex-vessel equipment to be maintained through conventional ``hands-on`` procedures. Second, to the maximum extent possible, low activation materials will be used inside the shielding volume. This resulted in the selection of Titanium (Ti-6Al-4V) for the vacuum vessel and PFC structures. The third decision stipulated that the primary in-vessel components will be replaced or repaired via remote maintenance tools specifically provided for the task. The component designers have been given the responsibility of incorporating maintenance design and for proving the maintainability of the design concepts in full-scale mockup tests prior to the initiation of final fabrication. Remote maintenance of the TPX machine is facilitated by general purpose tools provided by a special purpose design team. Major tools will include an in-vessel transporter, a vessel transfer system and a large component transfer container. In addition, tools such as manipulators and remotely operable impactmore » wrenches will be made available to the component designers by this group. Maintenance systems will also provide the necessary controls for this equipment.« less

Authors:
;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10178377
Report Number(s):
CONF-940630-42
ON: DE94017901
DOE Contract Number:
AC05-84OR21400; AC02-76CH03073
Resource Type:
Conference
Resource Relation:
Conference: 11. topical meeting on the technology of fusion energy,New Orleans, LA (United States),19-24 Jun 1994; Other Information: PBD: [1994]
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; TPX DEVICE; SHIELDING; MAINTENANCE; REMOTE HANDLING; REMOTE HANDLING EQUIPMENT; 700480; COMPONENT DEVELOPMENT; MATERIALS STUDIES

Citation Formats

Rennich, M.J., and Nelson, B.E.. TPX remote maintenance and shielding. United States: N. p., 1994. Web.
Rennich, M.J., & Nelson, B.E.. TPX remote maintenance and shielding. United States.
Rennich, M.J., and Nelson, B.E.. Thu . "TPX remote maintenance and shielding". United States. doi:. https://www.osti.gov/servlets/purl/10178377.
@article{osti_10178377,
title = {TPX remote maintenance and shielding},
author = {Rennich, M.J. and Nelson, B.E.},
abstractNote = {The Tokamak Physics Experiment machine design incorporates comprehensive planning for efficient and safe component maintenance. Three programmatic decisions have been made to insure the successful implementation of this objective. First, the tokamak incorporates radiation shielding to reduce activation of components and limit the dose rate to personnel working on the outside of the machine. This allows most of the ex-vessel equipment to be maintained through conventional ``hands-on`` procedures. Second, to the maximum extent possible, low activation materials will be used inside the shielding volume. This resulted in the selection of Titanium (Ti-6Al-4V) for the vacuum vessel and PFC structures. The third decision stipulated that the primary in-vessel components will be replaced or repaired via remote maintenance tools specifically provided for the task. The component designers have been given the responsibility of incorporating maintenance design and for proving the maintainability of the design concepts in full-scale mockup tests prior to the initiation of final fabrication. Remote maintenance of the TPX machine is facilitated by general purpose tools provided by a special purpose design team. Major tools will include an in-vessel transporter, a vessel transfer system and a large component transfer container. In addition, tools such as manipulators and remotely operable impact wrenches will be made available to the component designers by this group. Maintenance systems will also provide the necessary controls for this equipment.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 01 00:00:00 EDT 1994},
month = {Thu Sep 01 00:00:00 EDT 1994}
}

Conference:
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  • The Tokamak Physics Experiment (TPX) machine design incorporates comprehensive planning for efficient and safe component maintenance. Three programmatic decisions have been made to insure the successful implementation of this objective. First, the tokamak incorporates radiation shielding to reduce activation of components and limit the dose rate to personnel working on the outside of the machine. This allows most of the ex-vessel equipment to be maintained through conventional {open_quotes}hands-on{close_quotes} procedures. Second, to the maximum extent possible, low activation materials will be used inside the shielding volume. This resulted in the selection of Titanium (Ti-6Al-4V) for the vacuum vessel and Plasma Facingmore » Components (PFC) structures. The third decision stipulated that the primary in-vessel components will be replaced or repaired via remote maintenance tools specifically provided for the task. The component designers have been given the responsibility of incorporating maintenance design and for proving the maintainability of the design concepts in full-scale mockup tests prior to the initiation of final fabrication. Remote maintenance of the TPX machine is facilitated by general purpose tools provided by a special purpose design team. Major tools will include an in-vessel transporter, a vessel transfer system and a large component transfer container. In addition, tools such as manipulators and remotely operable impact wrenches will be made available to the component designers by this group. Maintenance systems will also provide the necessary controls for this equipment.« less
  • The Tokamak Physics Experiment (TPX), to be located at Princeton Plasma Physics Laboratory, will be a steady-state, high-performance fusion machine. It will use hydrogen fuel during its original operation, deuterium-deuterium (D-D) fuel for an extended intermediate period of time and then a limited number of runs using deuterium-tritium (D-T) fuel. The D-D operations wig generate neutron fluxes that will activate materials of the vacuum vessel. From that point on, the resulting ionizing radiation, which will continue to increase, particularly during D-T operation, will prevent personnel access into the vessel to perform either scheduled or unscheduled maintenance activities. All activities performedmore » within the vacuum vessel must be accomplished using remote means. TPX has taken a new approach for remote maintenance of the components within the vacuum vessel. This document describes the system that is being developed.« less
  • The Tokamak Physics Experiment (TPX) has used the lessons learned from successful remote maintenance and remote handling facilities to develop both a concept and philosophy for incorporation of remote design from the earliest phases of the project. Initiation of mockup testing during the conceptual design phase leads to significant improvements in the basic maintenance equipment configuration. In addition, remote handling features and capabilities have been incorporated into the design of the plasma-facing components (PFCs) as part of the total PFC design effort.
  • The Tokamak Physics Experiment (TPX), to be located at Princeton Plasma Physics Laboratory, will be a steady-state, high-performance fusion machine. It will use hydrogen fuel during its original operation, deuterium-deuterium (D-D) fuel for an extended intermediate period of time and then a limited number of runs using deuterium-tritium (D-T) fuel. The D-D operations wig generate neutron fluxes that will activate materials of the vacuum vessel. From that point on, the resulting ionizing radiation, which will continue to increase, particularly during D-T operation, will prevent personnel access into the vessel to perform either scheduled or unscheduled maintenance activities. All activities performedmore » within the vacuum vessel must be accomplished using remote means. TPX has taken a new approach for remote maintenance of the components within the vacuum vessel. This document describes the system that is being developed.« less
  • Radiation shielding analysis and design calculations were performed for remote maintenance cells of the proposed National Spallation Neutron Source (NSNS) facility. In the analysis, a calculational strategy utilizing coupled high energy Monte Carlo calculations and multi-dimensional discrete ordinates calculations was implemented to perform an activation analysis and shielding assessment of the NSNS remote handling cells. A general description of the remote maintenance cells, the methodology employed, and preliminary results of the shielding analysis and recommendations are presented.