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10 Years of CANDU-6 in Romania

10 Years of CANDU-6 in Romania. IFIN-HH: D. Galeriu, A. Melintescu, D. Slavnicu CNE-PROD: I. Popescu, E. Bobric. INTRODUCTION.

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10 Years of CANDU-6 in Romania

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  1. 10 Years of CANDU-6 in Romania IFIN-HH: D. Galeriu, A. Melintescu, D. Slavnicu CNE-PROD: I. Popescu, E. Bobric

  2. INTRODUCTION • In 1999, IFIN-HH researchers have been asked to introduce CANDU6 reactors in the context of an Int. Symposium “ Radiological impact assessment in South-Eastern Mediterranean Area” [1]. After refreshing the knowledge on CANDU6 radionuclide production and release into the environment, we used a published paper from S.Korea on the reactor physics of tritium production and release into the environment, based on Wolsong 1 experience [2] and a full paper was also published [3]. We have used specific data from Wolsong 1 : • Total heavy water inventory (M, kg) : 9.57 104 in coolant and 2.62 105 in moderator • Heavy water under neutron flux (m, kg): 6.03 103 in coolant and 1.92 105 in moderator • Neutron absorbtion cross section (, cm²) 3.4 10-28 in coolant and 4.19 10-28 in moderator • Thermal neutron flux (, cm¯²s¯¹) 1.235 10 14 in coolant and 2.3 10 14 in moderator • Average plant capacity factor 0.85 • Average escaped heavy water 18 t/y • Average escaped fraction from coolant 0.93 • Average recovery fraction 0.78

  3. Plant capacity factor

  4. T RELEASE TBq/y

  5. Source of release • Releases into the environments depend strongly on the source of escaped heavy water. Most of losses are from coolant with a low tritium specific activity. In the standard case we considered that 93 % of losses are from coolant with a recovery fraction of 0.78. In practice this figures have a range as it depend of many factors (vapor to liquid escape fraction, tubing and vanes fragility, human errors etc.) Based on past experience we asses the coolant contribution can vary between 0.91 and 0.97 in normal plant operation conditions • We compare the measured release to the environment ( atmospheric + liquid) with model calculation under the above range of coolant contribution- see figure

  6. On average, liquid releases are 61% from total but varies significantly

  7. The unit 2 will be fully operated in 2008, unit 3 in 2013 and unit 4 in 2014. NO DETRITIATION

  8. RELEASE COMPARISON ROKKASHO AND LA HAGUE TARGETS ARE <30 microSv/y for public

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