Volume 3, Issue 1

Original research papers

Radiation Protection

REMOTE CONTROL ROBOT FOR DECOMMISSIONING HORIZONTAL FUEL CHANNELS OF NUCLEAR REACTOR

Constantin Popescu, Gabi Rosca-Fartat, Nicolae Pana, Daniela Fluerasu

Pages: 34-40

DOI: 10.21175/RadJ.2018.01.007

Received: 23 FEB 2017, Received revised: 24 MAY 2017, Accepted: 5 JUN 2017, Published online: 2 APR 2018

The authors’ contribution to this paper is to present a possible designing solution concept of the remote control robot for the decommissioning of the nuclear reactor horizontal fuel channels. In this paper, the authors present several properties of geometry, kinematics and dynamics of the robot movement into the reactor fuel channel and a few considerations required due to material thickness, according to the radiation protection procedures. The main stages of the dismantling operation in terms of operational safety are: positioning, coupling and locking, operating accordingly with the approved decommissioning procedures, sorting and storing the extracted items in the robot container. All operating steps are designed to be automated and performed by one robot which shall provide radiation protection during the dismantling stages, thus ensuring radiation protection of the workers. The operations are monitored by internal sensors and transducers, by pyrometer for temperature during the cutting process and video surveillance cameras for the dismantling components, in order to ensure assembly of operating facilities and a permanent control. The remote control robot radiation protection has a safety system able to extract the robot from the channel in case of a disruption of the blocking or decommissioning activities due to any error registered, in order to ensure the environmental and workers’ protection.
  1. Assessment and management of ageing of major nuclear power plant components important to safety: CANDU reactor assemblies, IAEA-TECDOC-1197, IAEA, Vienna, Austria, 2001.
    Retrieved from: https://www-pub.iaea.org/MTCD/publications/PDF/te_1197_prn.pdf;
    Retrieved on: Jan. 10, 2018
  2. Decommissioning of Nuclear Power Plants and Research Reactors, IAEA Safety Standard Series No. WS-G-2.1, IAEA, Vienna, Austria, 1999.
    Retrieved from: https://www-pub.iaea.org/MTCD/Publications/PDF/P079_scr.pdf;
    Retrieved on: Jan. 10, 2018
  3. Atomic Energy of Canada Limited, AECL, Ottawa, Canada, 2014.
    Retrieved from: http://www.aecl.ca/en/home/news/news-archives/2014-10-10-launch-of-canadian-nuclear-
    laboratories.aspx
    ;
    Retrieved on: Jan. 10, 2018
  4. Nuclear Power Plant Design Characteristics, IAEA-TECDOC-1544, IAEA, Vienna, Austria, 2007.
    Retrieved from: https://www-pub.iaea.org/MTCD/Publications/PDF/te_1544_web.pdf;
    Retrieved on: Jan. 10, 2018
  5. B. A. Cheadle, E. G. Price, “Operating performance of CANDU pressure tubes,” presented at the IAEA Technical Committee Meeting on the Exchange of Operational Safety Experience of Heavy Water Reactors, Vienna, Austria, Feb. 1989.
    Retrieved from: http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/23/059/23059653.pdf;
    Retrieved on: Jan. 10, 2018
  6. K. Heyde, Basic Ideas and Concepts in Nuclear Physics: an introductory approach, Bristol, UK: Institute of Physics Publishing, 1994.
    Retrieved from: http://www.fisica.net/nuclear/basic_ideas_and_concepts_in_nuclear_physics_
    an_introductory_approach.pdf
    ;
    Retrieved on: Jan. 10, 2018
  7. R. G. Steed, Nuclear Power in Canada and Beyond, Renfrew, Canada: General Store Publishing House, 2007.
  8. Fundamentals of power reactors, AECL, Ottawa, Canada, 1993.
    Retrieved from: https://canteach.candu.org/Content%20Library/Forms/AllItems.aspx;
    Retrieved on: Jan. 10, 2018
  9. ANSTO Replacement Research Reactor Project: SAR Chapter 19 – Decommissioning, Rep. RRRP-7225-EBEAN-002-REV0-CHAPTER-19, ANSTO, Sydney, Australia, 2004.
    Retrieved from: https://www.arpansa.gov.au/sites/g/files/net3086/f/legacy/pubs/regulatory/opal/op/SAR/ch19.pdf;
    Retrieved on: Jan. 10, 2018
  10. Enhanced CANDU 6: Technical Summary, SNC-LAVALIN, Montreal, Canada, 2015.
    Retrieved from: http://www.snclavalin.com/en/files/documents/publications/enhanced-candu-6-technical-
    summary_en.pdf
    ;
    Retrieved on: Jan. 10, 2018
  11. National Commission for Nuclear Activities Control. (Oct. 10, 1996). Law no. 111/1996 on the safe deployment, regulation, authorization and control of nuclear activities.
    Retrieved from: http://www.cncan.ro/assets/Legislatie/Law-no-111-of-19962006-final.doc;
    Retrieved on: Jan. 10. 2018
  12. Comisia Nationala pentru Controlul Activitatilor Nucleare. (15.9.2002). NSN-15 Normele de dezafectare a obiectivelor și instala țiilor nucleare. (National Commission for Nuclear Activities Control. (Sep. 9, 2002). NSN-15 Rules for the decommissioning of objectives and nuclear installations.)
    Retrieved from: http://www.cncan.ro/assets/nsn/nsn15.pdf;
    Retrieved on: Jan. 15, 2018
  13. S. Venkatapathi, A. Mehmi, H. Wong, “Pressure tube to end fitting roll expanded joints in CANDU PHWRS,” presented at the Int. Conf. on Expanded and Rolled Joint Technology, Toronto, Canada, Sep. 1993.
  14. Assessment and management of ageing of major nuclear power plant components important to safety: CANDU reactor assemblies, IAEA-TEDOC-1197, IAEA, Vienna, Austria, 2001.
    Retrieved from: https://www-pub.iaea.org/MTCD/publications/PDF/te_1197_prn.pdf;
    Retrieved on: Jan. 10, 2018
  15. Organization and Management for Decommissioning of Large Nuclear Facilities, IAEA Technical Reports Series No. 399, IAEA, Vienna, Austria, 2000.
    Retrieved from: https://www-pub.iaea.org/MTCD/Publications/PDF/TRS399_scr.pdf;
    Retrieved on: Jan. 10, 2018
  16. Selection of decommissioning strategies: Issues and factors, IAEA-TECDOC-1478, IAEA, Vienna, Austria, 2005.
    Retrieved from: https://www-pub.iaea.org/MTCD/publications/PDF/TE_1478_web.pdf;
    Retrieved on: Jan. 11, 2018
  17. State of the Art Technology for Decontamination and Dismantling of Nuclear Facilities, IAEA Technical Reports Series No. 395, IAEA, Vienna, Austria, 1999.
    Retrieved from: https://www-pub.iaea.org/mtcd/publications/pdf/trs395_scr/d395_part1_scr.pdf;
    Retrieved on: Jan. 11, 2018
  18. Water channel reactor fuels and fuel channels: Design, performance, research and development, IAEA-TECDOC-997, IAEA, Vienna, Austria, 1996.
    Retrieved from: https://www-pub.iaea.org/MTCD/publications/PDF/te_997_prn.pdf;
    Retrieved on: Jan. 11, 2018
  19. Heavy Water Reactors: Status and Projected Development, IAEA Technical Reports Series No. 407, IAEA, Vienna, Austria, 2002.
    Retrieved from: https://www-pub.iaea.org/MTCD/publications/PDF/TRS407_scr/D407_scr1.pdf;
    Retrieved on: Jan. 15, 2018
  20. Preliminary decommissioning plan for the Point Lepreau generating station, Rep. N29-1387-003, TLG Services, Inc. Bridgewater (CT), USA, 2010.