Advertisement

Prevention of Human Factors and Reliability Analysis in Operating of Sipping Device on IPR-R1 TRIGA Reactor, a Study Case

  • Maritza Rodriguez GualEmail author
  • Rogerio Rival Rodrigues
  • Vagner de Oliveira
  • Claudio Lopes Cunha
Chapter
Part of the Springer Series in Reliability Engineering book series (RELIABILITY)

Abstract

The new sipping device constructed at Centro de Desenvolvimento da Tecnologia Nuclear—CDTN (Nuclear Technology Development Center—CDTN), Belo Horizonte, Brazil will be used to inspect irradiated fuel elements cladding in the IPR-R1 TRIGA reactor. The sipping test method is important to check the integrity of the irradiated fuel elements cladding of this reactor, which may be affected by corrosion over long periods of time. The sipping test identifies failed fuel elements by measuring Cs-137 radioactive metal ion activity in the surrounding water, collected via the sipping device. This chapter describes the application of the “what if” technique for assessing risk and reliability in sipping test operations, including an analysis to identify human error and equipment failure modes. Results show initiating events, consequences, and recommended safeguards. In addition, measures to reduce human error are also provided. Human error has been identified as the primary cause or contributing factor in failure modes.

Keywords

Component failure modes Risk assessment Sipping test IPR-R1 TRIGA reactor “What if” technique 

Notes

Acknowledgments

This study was supported and funded by the following organizations: Nuclear Technology Development Center, Brazilian Nuclear Energy Commission (CNEN), Research Support Foundation of the State of Minas Gerais (FAPEMIG), Brazilian Council for Scientific and Technological Development (CNPq), and Coordination for Improvement of Higher Education of Personnel (CAPES).

References

  1. Alverbro K, Nevhage B, Erdeniz R (2010) Methods for risk analysis. Printed in Sweden by US AB, Stockholm. ISSN 1652-5442Google Scholar
  2. Borio di Tigliole A, Cagnazzo M, Lana F, Losi A, Magrotti G, Manera S, Marchetti F, Pappalardo P, Salvini A, Vinciguerra G (2004) Identification of a leaking TRIGA fuel element at the reactor facility of Pavia, Vienna University of Technology, Atomic Institute of the Austrian Universities (Austria), 207 p; pp 53–61, INIS-AT--0076, 2nd World TRIGA users conference; Vienna, Austria, 15–18 Sep 2004
  3. Castañeda JG, Delfín LA, Alvarado PR, Mazón RR, Ortega Velázquez B (2003) Diseño y Construcción del SIPPING para Combustibles del Reactor Triga Mark III, Energía Nuclear y Seguridad Radiológica: Nuevos Retos y Perspectivas XIV Congreso Anual de la SNM/XXI Reunión Anual de la SMSR. Guadalajara, Jalisco, México, 10–13 de Septiembre, CDROM (In Spanish)Google Scholar
  4. CNEN Comissão Nacional de Energia Nuclear (2011) Basic guidelines on radiological protection, CNEN-NN-3.01 regulatory position 3:01/004:2011. Dose constraint, occupational reference levels and area classification, Rio de Janeiro, 2011 (in Portuguese)Google Scholar
  5. Costa ACL, Ribeiro E, da Silva LL (2011) Articulated clamp for handling devices and equipment at a distance. Brazilian Patent No. PI0803376-5 A2, October, 2011Google Scholar
  6. Doerr WW (1991) What-if analysis. In: Greenberg HR, Cramer JJ (eds) Risk assessment and risk management for the chemical process industry. Van Nostrand Reinhold, New York, pp 75–90Google Scholar
  7. Dyah Sulistyani, Suryantoro R (2015) Integrity Test of the SNF Using Sipping Test Method, The 2015 FNCA Workshop on Radiation Safety & Radioactive Waste Management (RS&RWM), 17–19 Nov, Serpong, Indonesia,Google Scholar
  8. Gual MR, Mesquita AZ, Campolina DAM, Rodrigues RR (2016) Dosimetry assessment during the sipping test in the IPR-R1 TRIGA reactor using MCNPX. Prog Nucl Energy 93:238–245.  http://dx.doi.org/10.1016/j.pnucene.2016.09.002 CrossRefGoogle Scholar
  9. Gual MR, Perdomo OM, Salomón J, Wellesley J, Lora A (2014) ASeC software application based on FMEAe in a mechanical samples positioning system on a radial channel for irradiations in a nuclear research reactor with continuous full-power operation. Int J Ecosyst Ecol Sci (IJEES) 4(1):81–88Google Scholar
  10. Guidance Notes on Risk Assessment Applications for the Marine and Offshore Oil and Gas Industries. American Bureau of Shipping, ABS Plaza, Jun 2000Google Scholar
  11. IAEA Bulletin. WHAT IF? ICRP guidance on potential radiation exposure, 41/3/1999Google Scholar
  12. Jafari M, Gholizadeh Aghoyeh R, Toumari R, Khalafi H (2015) A sipping test simulator for identifying defective fuels in MTR type nuclear research reactor. Ann Nucl Energy 77:238–245Google Scholar
  13. NEA/CSNI/R (2014) 10 (2014) Leaking fuel impacts and practices, nuclear energy agency. Committee on the Safety of Nuclear Installations, 18 Jul 2014.Google Scholar
  14. Park J-Y, Shim M-S, Lee J-H (2014) Current status of integrity assessment by sipping system of spent fuel bundles irradiated in CANDU reactor. Nucl Eng Technol 46(6). doi: 10.5516/NET.09.2014.018
  15. Perdomo OM, Salomón LJ (2016) Expanded failure mode and effects analysis: advanced approach for reliability assessments. Revista Cubana de Ingeniería VII (2):5–14Google Scholar
  16. Perrotta JA, Terremoto LAA, Zeituni CA (1998) Experience on wet storage spent fuel sipping at IEA-R1 Brazilian research reactor. Ann Nucl Energy 25(45):237–258. https://doi.org/10.1016/S0306-4549(97)00039-X CrossRefGoogle Scholar
  17. Rodrigues RR (2016) Development and methodology implementation for integrity structural assessment of IPR-R1 TRIGA nuclear reactor fuel element by sipping method. Thesis project (in Portuguese)Google Scholar
  18. Slugeň V, Mikloš M, Božik M, Vašina D (2007) Monitoring and Leak testig of WWER-440 fuel assemblies in Slovak wet interim spent fuel storage facility. Acta Montanistica Slovaca Ročník 12(1):187–191Google Scholar
  19. Terremoto LA, Zeituni CA, Perrotta JA, da Silva JER (2000) Gamma-ray spectroscopy on irradiated MTR fuel elements. Nucl Instrum Methods in Phys Res Sect A 450(2–3):495–514CrossRefGoogle Scholar

Copyright information

© Springer International Publishing AG 2018

Authors and Affiliations

  • Maritza Rodriguez Gual
    • 1
    Email author
  • Rogerio Rival Rodrigues
    • 1
  • Vagner de Oliveira
    • 1
  • Claudio Lopes Cunha
    • 1
  1. 1.Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN)Belo HorizonteBrazil

Personalised recommendations