Evaluation of the activity of irradiated graphite in the Ignalina Nuclear Power Plant RBMK-1500 reactor

• Autorzy: Ancius D. , Ridikas D. , Remeikis V. , Plukis A. , Plukiene R. , Cometto M.
• Języki publikacji: EN

Abstrakty

EN

Ignalina NPP Unit 1 with the RBMK-1500 type reactor enters the preparatory stage for its decommissioning. A big volume of graphite has to be dismantled and managed. This paper evaluates the composition of radionuclides in irradiated graphite on the basis of the calculation scheme with computer codes MCNPX and CINDER'90. Full scale calculations take into account the whole energy spectrum of neutrons, the spatial neutron flux in different reactor structures and the impurities of RBMK-1500 graphite measured by two independent methods. Principal contributors to the total activity as well as other radionuclides important from the radiological point of view are identified. The uncertainties of such calculations are discussed.

Słowa kluczowe

EN

modeling; activation analysis; radioactive waste; graphite

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2005
• Tom: Vol. 50, nr 3
• Strony: 113--120
• Opis fizyczny: Bibliogr. 17 poz., rys.

Twórcy

autor

Ancius D.

• Institute of Physics, 231 Savanoriu Ave., LT-02300 Vilnius, Lithuania, Tel.: + 370 5 266 1640, Fax: + 370 5 260 2317

autor

Ridikas D.

• CEA Saclay, DSM/DAPNIA/SPhN, F-91191 Gif-sur-Yvette, France

autor

Remeikis V.

• Institute of Physics, 231 Savanoriu Ave., LT-02300 Vilnius, Lithuania, Tel.: + 370 5 266 1640, Fax: + 370 5 260 2317

autor

Plukis A.

• Institute of Physics, 231 Savanoriu Ave., LT-02300 Vilnius, Lithuania, Tel.: + 370 5 266 1640, Fax: + 370 5 260 2317

autor

Plukiene R.

• Institute of Physics, 231 Savanoriu Ave., LT-02300 Vilnius, Lithuania, Tel.: + 370 5 266 1640, Fax: + 370 5 260 2317

autor

Cometto M.

• CEA Saclay, DSM/DAPNIA/SPhN, F-91191 Gif-sur-Yvette, France

Bibliografia

• 1. Almenas K, Kaliatka A, Ušpuras E (1998) Ignalina RBMK-1500. A source book, 2nd ed. ISAG Lithuanian Energy Institute, Kaunas.
• 2. Behrens D, Alexeev N, Davydova G et al. (1998) The Monte Carlo codes MCNP and MCU for RBMK criticality calculations. Nucl Eng Des 183:287−302.
• 3. Brié M (1993) Caractérisation du graphite des empilements et chemises des éléments combustibles. Etude bibliographique. CEA, Saclay.
• 4. Briesmeister JF (for Group X-6 MCNP-A) (1993) A general Monte Carlo code for neutron and photon transport. Version 4A. LANL, Report LA-12625-M.
• 5. Brown FJ, Palmer JD, Wood P (1999) Derivation of a radionuclide inventory for irradiated graphite-chlorine-36 inventory determination. In: Proc of IAEA Technical Committee Meeting held in Manchester, 18−20 October, 1999, Manchester, UK. IAEA, Vienna, pp 143−152.
• 6. Buchuev AV, Verzilov YN, Zubarev VN et al. (1999) Radionuclide characterisation of graphite stacks from plutonium production reactors of the Siberian group of chemical enterprises. In: Proc of IAEA Technical Committee Meeting held in Manchester, 18−20 October 1999, Manchester, UK. IAEA, Vienna, pp 160−175.
• 7. Buchuev AV, Zubarev VN, Prochin IM (2002) Composition and quantity of impurities in graphite of industrial reactors. Atomnaya energiya 92;4:298−302 (inRussian).
• 8. Bylkin BK, Davydova GB, Zverkov YA et al. (2001) Induced radioactivity and waste classification of reactor zone components of the Chernobyl Nuclear Power Plant Unit 1 after final shut down. Nucl Technol 136:76−88.
• 9. Cometto M, Ancius D, Ridikas D (2003) Testing of different data libraries in activation analysis of concrete and graphite from nuclear installations. In: Proc of the Int Workshop on Nuclear Data for the Transmutation of Nuclear Waste, 1−5 September 2003, GSI-Darmstadt, Germany, http://www-wnt.gsi.de/TRAMU.
• 10. Cometto M, Ridikas D, Aubert MC, Damoy F, Ancius D (2005) Activation analysis of concrete and graphite in the experimental reactor RUS. Radiat Prot Dosim (inprint).
• 11. Linsley G (for the division NFCWM IAEA) (1996) Clearance levels for radionuclides in solid materials. Application of exemption principles. IAEA-TECDOC-855. IAEA, Vienna.
• 12. Remeikis V, Jurkevicius A (2004) Evolution of the neutron sensor characteristics in the RBMK-1500 reactor neutron flux. Nucl Eng Des 231;3:271−282.
• 13. Revel G (1999) Analyse par activation. Technique de l’Ingénieur, Laboratoire Pierre-Sue. CRNS-CEA, Doc P 2 565-10.
• 14. Šmaižys A, Narkunas E, Poškas P (2004) Evaluation of neutron activation processes in RBMK-1500 reactor’s graphite. Lithuanian J Phys 43;6:499−503.
• 15. Tsyplenkov V (for the division NFCWM IAEA) (1996) Requirements and methods for low and intermediate level waste package acceptability. IAEA-TECDOC-864.IAEA, Vienna.
• 16. Virgiliev JS, Vlasov KP (1994) Impurities in construc-tional graphite. Chem Solid Fuel 3:87−96.
• 17. Wilson WB, England TR, Van Riper KA (1999) Status of CINDER’90 codes and data. Los Alamos National Laboratory. Preprint LA-UR-99-361.