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Tritium Release Reduction based on Release Trend Analysis. JASON SHIN Korea Hydro & Nuclear Power co. Location of Wolsong NPP II. Wolsong NPP II has 2 units, Unit 3 & 4. They are PHWRs (Pressured Heavy Water Reactors). They generate and release tritium. Uljin. Yonggwang. Wolsong. Kori.

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Tritium Release Reduction based on Release Trend Analysis


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    1. Tritium Release Reductionbased on Release Trend Analysis JASON SHIN Korea Hydro & Nuclear Power co.

    2. Location of Wolsong NPP II • Wolsong NPP II has 2 units, Unit 3 & 4. • They are PHWRs (Pressured Heavy Water Reactors). • They generate and release tritium. Uljin Yonggwang Wolsong Kori

    3. GEM Reactor Building Service Building Spent Fuel Bay VentilationSystem of Wolsong 3 & 4 one common stack for the effluence from 3 controlled areas

    4. Monthly Release of Airborne Tritium • Increase amount from Unit 3’s release sustained compared to Unit 4’s • What would be the cause?

    5. Ambiguity on Tritium Release of Unit 3 & 4 • Unit 3’ tritium concentration in air of the reactor building was a little higher than unit 4’s. (not more than 1.5 times) • But Unit 3’ tritium release was much higher than unit 4’s. (more than 2 times) ※ There was an event at unit 4 in March-2009, but it has no relation with the theme.

    6. Respective Tritium Releasefrom the 3 Controlled Area • Investigated tritium release rates respectively from Reactor Building, Service Building and Spent Fuel Bay • Dominant release was from RB as expected

    7. Analysis Release Rate versus Concentration • In-depth study for relationship between tritium release rate versus airborne concentrations in RB

    8. R201 and R002 vs Other Areas • Unit 3’ concentrations in R201 and R002 were lower but much higher than unit 4’s.

    9. R201 and R002 vs Other Areas • Proportionality of the release rate was sensitive with the concentrations in R201 and R002 compare to the other areas.

    10. The Reason Why R201 • R107, R108, R501 areas have high tritium concentration but low vent flow • R201, R002 areas have low tritium concentration but high vent flow ※ Air of R002 was flown from R201: both airborne concentrations are similar R107, R108, R501 Areas R201, R002 Areas

    11. Assessment of Tritium Release Rate • Analysis of measurement data of tritium concentration and designed flow rates of controlled areas Release Rate = Σ(Local Concentrationi x Vent Flowi) Stack R501 & Adjacent Rooms R107, R108 Reactor Building Service Building R201 & Adjacent Rooms Spent Fuel Bay R002 & Adjacent Rooms

    12. Tritium Release Measurements vs Estimate • The measured release roughly agreed with estimated value but there was a little difference at unit 3.

    13. Possible Assumption • leak of heavy water containing lots amount tritium in R201 • Some small leak as 0.1L of heavy water could cause dominant portion of daily tritium release, especially with the Moderator. • The leak should be near ventilations. • This could explain the difference between the measurement and the estimate for release rate.

    14. Intensive Survey on R201 • It is difficult to find the leak point because heavy water evaporates easily and spreads out quickly in the wide area of R201 • We divided R201 into many divisions and checked tritium concentration each division.

    15. Leak Points • There were 2 positions which have high tritium concentration. • Found 2 leak points on Liquid Injection System related to the Moderator System. 0.8 0.8 1.0 0.7 1.2 1.3 1.5 0.8 1.1 3.1 3.1 280* 6.1 46 1.4 * concentration inside an envelope wrapping equipment

    16. Airborne Tritium Concentration after Repair • After repair, airborne tritium concentration in R201 went down.

    17. Tritium Release Rate after the Repair • The tritium release rate decreased some • But it was not enough as expected after repairing. • Potentially additional leak near vents which has not affected local concentration measurement.

    18. Further Research • Reviewed further potential leak points near vents. • Special attention to R402 which has many devices related to Moderator System and vents. • R402 was located beside R201 and there was no wall between R402 and R201. Vent flow R406 R402 R201 R403 R405

    19. Intensive Survey on R402 • We collected samples and measured the tritium concentrations at every spot in R402 1.4 1.5 1.4 2.2 2.1 1.5 1.3 10.8 2.2 2.7 1.3 1.4 1.8 1.8 1.3 3.4 2.4 1.4 1.8 1.4

    20. Leak Point in R402 • We found a leaking valve of Poison Addition System related to the Moderator System also. • After we repaired it…

    21. The Final Effect • Tritium release rate dropped a half of the previous one. • From RB it dropped to be a third of the previous rate and reached the expected level

    22. Conclusion • We can evaluate the release rate of radioactive material using regular measurements of local concentration with comparing to the designed vent flow rates. • This method is useful to search leak points and lead to reduce the release rate.

    23. Thanks for your attention. Do you have any questions?