NDLI: Health physics and radioactive waste considerations for the TFTR

Content Provider	IEEE Xplore Digital Library
Author	Rule, K. Gilbert, J. Scott, J. Ascione, G. Cislo, R. Elwood, S. Fournoy, R. Larson, S. Parsells, R. Stencel, J. Tilson, C.
Copyright Year	1995
Description	Author affiliation: Plasma Phys. Lab., Princeton Univ., NJ, USA (Rule, K.; Gilbert, J.; Scott, J.; Ascione, G.; Cislo, R.; Elwood, S.; Fournoy, R.; Larson, S.; Parsells, R.; Stencel, J.; Tilson, C.)
Abstract	The Tokamak Fusion Test Reactor (TFTR) began high power fusion operations, with tritium, in November of 1993. These operations utilize a 50/50 mixture of deuterium and tritium which yields 14 MeV neutrons at a magnitude of 2.0E+18 per 3 second pulse. These high energy neutrons interact with the vacuum vessel, neutral beams, confinement coils and other structural and peripheral materials resulting in fusion activation products. These operations also consist of the delivery, storage, injection and subsequent processing of tritium gas in support of the D-T fusion program. These systems have manipulated and processed 208 PBq of tritium throughout the past year. The operational health physics program involves maintenance on activated materials and tritium contaminated systems. Survey data and findings are collected on routine and special maintenance situations ranging from work on small volume piping to large volume neutral beam systems. The results of radiological measurements are described in relation to the differentiation of elemental tritium to tritium oxide in worker's breathing zones and the associated general work area. The contamination levels, airborne radioactivity, and oil concentrations are also compared. Measurements for gamma radiation are performed to determine personnel access requirements and for comparison to activation and decay models as a planning tools. TFTR presents many unusual challenges with regard to dismantling, packaging and disposal of its components and ancillary systems. A functional time phased radioactive waste generation schedule was developed to enhance project planning. This project will be the first demonstration of the decommissioning of a tritium fuelled fusion test reactor.
Starting Page	626
Ending Page	629
File Size	457475
Page Count	4
File Format	PDF
ISBN	0780329694
DOI	10.1109/FUSION.1995.534302
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	1995-09-30
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Radiation monitoring Radioactive waste Testing Inductors Neutrons Pollution measurement Tokamaks Deuterium Elementary particle vacuum Coils
Content Type	Text
Resource Type	Article

Sl.	Authority	Responsibilities	Communication Details
1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
5	Website/Portal (Helpdesk)	Queries regarding NDLI and its services	support@ndl.gov.in
6	Contents and Copyright Issues	Queries related to content curation and copyright issues	content@ndl.gov.in
7	National Digital Library of India Club (NDLI Club)	Queries related to NDLI Club formation, support, user awareness program, seminar/symposium, collaboration, social media, promotion, and outreach	clubsupport@ndl.gov.in
8	Digital Preservation Centre (DPC)	Assistance with digitizing and archiving copyright-free printed books	dpc@ndl.gov.in
9	IDR Setup or Support	Queries related to establishment and support of Institutional Digital Repository (IDR) and IDR workshops	idr@ndl.gov.in

Structural analysis of TFTR TF coils and support structure for 6 Tesla operation

SF/sub 6/ and water cold trap for TFTR deuterium-tritium operations

TFTR status and plans

TFTR DT preparation project status

Operation of a Fluorinert cooling system for the TFTR TF coils and TFTR Coil Flowswitch Monitoring System modification to accommodate the TF Alternate Cooling System (Fluorinert)

Overview of the TFTR D&D program

Plasma studies for an upgraded TFTR experiment

Tritium recovery from the TFTR vessel

Neutron - Production And Detection On The TFTR Tokarnak During Dt Operation

Health physics and radioactive waste considerations for the TFTR

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