Research Reactor
| Types of facilities | ||
|---|---|---|
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Displacement of fuel plates from their normal position in fuel assemblies during normal operation of research reactor |
During a routine core video inspection at end of the operating program 005 the team discovered three plates of three different fuel assemblies being displaced from their nominal positions by some 25mm, 250mm and 400mm respectively. No release of fission products was detected. For more details, please see the Attachment of this form.
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Potential Extremity Overexposure at Texas A&M Research Reactor |
The licensee reported that an employee at the Texas A&M Nuclear Science Center received 75,800 mRem (758 mSv) to the extremities during the month of January 2006. Furthermore, the licensee reported that the individual also received 37,540 mRem (375.4 mSv) to the extremities during the month of February 2006. The licensee reported that the employee was involved in neutron activation analysis work involving contact lenses and that all ALARA procedures were strictly enforced.
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Switch off of a protection device during periodic inspection |
On the 2nd of October 1998, while the Phebus reactor was in shutdown, the protection system was completely switched off during a periodic inspection of control rods.
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Slightly increased radioactivity release outside the reactor while preparing for removal of leaky fuel assembly |
On 25.07.97 MIR- M1 pool type pressure tube research reactor (mainly used for materials testing purposes) was shut down because of increased activity indications of the Burst Can Detection System (BCDS) caused by depressurization of the operating fuel assembly (FA).
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Leakage of water in the primary cooling system of AERE Reasearch Centre |
On the morning of 14 July 1997 during the pre-start-up surveillance, it was found that the reactor pool water level had dropped by about 7.5 cm. The loss rate was increasing. On subsequent investigation it was detected that a portion of N-16 decay tank had got corroded/perforated. the leakage rate has presently been contained to 50 gallons per day. Total loss of primary water till to date (24.7.97) is estimated to be about 650 gallons. No fission but the only activated product Co-58 of about 27 Bq/litre so far has been found in the leaked water.
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Reactor scram followed by the actuation of safety valve in the reactor primary circuit |
At 11:15 (Moscow time) during research reactor operation at the preset power level Nt-200 MWt (Ne-48 MW) reactor protection on the "turbine trip" signal actuated due to failure in the turbine protection system circuit. The reactor was brought to subcriticality and simultaneously, according to design algorithm, the second scram system actuated to inject boric acid solution from the Safety Injection Tank (SIT) by compressed nitrogen action. During the transient reactor pressure dropped from 5.0 MPa to 4.8 MPa and then started to build up.
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OVEREXPOSURE OF A WORKER AT THE RESEARCH REACTOR R2-0 IN STUDSVIK AT UPPSALA UNIVERSITY'S NEUTRON RESEARCH FACILITY |
At the research reactor R2-0 in Studsvik at Uppsala University's Neutron Research Facility, the adjustment of a research equipment was not carefully performed. One person received about 50 mSv at one occasion. The same person during the year (from January to September) accumulated 23 mSv.
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PROBLEM IN LOWERING FRESH FUEL BUNDLE IN THE REACTOR |
Dhruva reactor was in shutdown state since 24.8.94 for refuelling and other maintenance works. After removal of irradiated assembly, when a fresh fuel assembly was being lowered in pile position K-13, the assembly could not be lowered beyond the gauge ring region. Several attempts were made with wet storage block. The fresh fuel assembly which had seen the obstruction in the pile was inspected, and it was found that one of the 5 leaves of the bottom bulge had got bent.
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POWER EXCURSION AT MCMASTER NUCLEAR RESEARCH REACTOR DURING FUEL LOADING |
A power excursion, which resulted in a reactor trip on overpower, occurred at the McMaster Nuclear Reactor (MNR) during a refuelling operation. MNR is a pool type research reactor currently operating at 2 MW. Following replacement of a shim safety rod control assembly, the fuel assemblies were being returned to the core. After loading the 5th fuel assembly, the shim safety rods were withdrawn to check that the reactor was not critical. The rods were then driven to the 85% withdrawn position instead of required 40% (safeguard position).
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ACCIDENT CLOSE TO THE FORMER RAPSODIE REACTOR AT THE CADARACHE SITE |
On 31. March 1994 towards 5:45 pm an explosion took place in rooms adjoining the former Rapsodie reactor.
The shock wave which followed the explosion caused a 300 sqm concrete slab to fall, destroying the circular adit located nearby. The dead body of a worker was discovered under the slab towards 10:30 p.m.. Four workers were rushed to the Manosque and Aix hospitals with multiple fractures.
This explosion was probably due to the hydrogen released following treatment of the slightly contaminated sodium with alcohol.
