Published 2010 | Version v1
Report

Beam port leakage problem in the BAEC TRIGA Mark-II research reactor and the corrective measures implemented

  • 1. Reactor Operation and Maintenance Unit, Atomic Energy Research Establishment (AERE), Savar, Dhaka (Bangladesh)
  • 2. Reactor and Neutron Physics Division, Institute of Nuclear Science and Technology (NST), Atomic Energy Research Establishment (AERE), Savar, Dhaka (Bangladesh)
  • 3. Health Physics and Radioactive Waste Management Unit, INST, Atomic Energy Research Establishment (AERE), Savar, Dhaka (Bangladesh)

Description

The 3MW TRIGA Mark-II research reactor (RR) of Bangladesh Atomic Energy Commission (BAEC), which has been in operation since 1986, has four Beam Ports (BPs). One of the BPs, which remained plugged with the beam port plugs (mainly a graphite shield plug) for about 23 years, was found to be leaking when its plugs were removed for installation of a high resolution powder diffractometer in it. The leak, which was developed because of corrosion, was found in the aluminum part of the BP, which is located inside the reactor pool at a depth of about 8 m. Condensate accumulated in the annular space between the graphite plug and inner wall of the aluminum beam port initiated the corrosion. The graphite plug, which got stuck very tightly inside the BP, was removed using locally designed and fabricated hand tools. Leakage of water came to the notice of the reactor operation personnel a couple of days after the beam port had been cleared. Water leakage was stopped by installing a split type encirclement clam around the damaged part of the BP by some remote handling mechanisms, designed and fabricated locally. The paper presents in detail the description of the leakage problem and the remedial measures implemented so as to make the reactor operational again after about 16 months. (author)

Part of:
Technical meeting on assessment of core structural materials and surveillance programme of research reactors. Program and abstracts

Additional details

Publishing Information

Imprint Title
Technical meeting on assessment of core structural materials and surveillance programme of research reactors. Program and abstracts
Imprint Pagination
43 p.
Journal Page Range
p. 15
Report number
IAEA-TM--40035

Conference

Title
Technical meeting on assessment of core structural materials and surveillance programme of research reactors
Dates
14-18 Jun 2010
Place
Vienna (Austria)

Optional Information

Notes
Abstract only