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Segmentation strategies for the irradiated and tritium contaminated PPPL TFTR

Conference ·
OSTI ID:46716
 [1];  [2];  [3]
  1. Princeton Univ., NJ (United States). Plasma Physics Lab.
  2. Advanced Consulting Group, Inc., Chicago, IL (United States)
  3. RHD Consultants, Inc., Princeton, NJ (United States)
+ Show Author Affiliations
The Tokamak Fusion Test Reactor (TFTR) at Princeton Plasma Physics Laboratory is scheduled to complete its final experiments in the Fall of 1995. As a result, the TFTR will be activated and tritium contaminated. After the experiments are complete, the TFTR will undergo Shutdown and Removal (S and R). The space vacated by the TFTR will be used for a new test reactor, the Tokamak Physics Experiment (TPX). Remote methods may be required to remove components and to segment the Vacuum Vessel. The TFTR has been studied to determine alternatives for the segmentation of the Vacuum Vessel from the inside (In-Vessel). The methodology to determine suitable strategies to segment the Vacuum Vessel from In-Vessel included several areas of concentration. These areas were segmentation locations, cutting/removal technologies, pros and cons, and cutting/removal technology delivery systems. The segmentation locations for easiest implementation and minimal steps in cutting and removal have been identified. Each of these will also achieve the baseline for packaging and shipment. The methods for cutting and removal of components were determined. In addition, the delivery systems were conceptualized.
Research Organization:
Princeton Univ., NJ (United States). Plasma Physics Lab.
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC02-76CH03073
OSTI ID:
46716
Report Number(s):
PPPL-CFP--3231; CONF-950414--1; ON: DE95009626
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BUILDINGS
DEMOLITION
LOW-LEVEL RADIOACTIVE WASTES
PLANNING
REMOTE HANDLING
SHUTDOWN
TFTR TOKAMAK
VACUUM SYSTEMS