Activation product transport using TRACT: ORE estimation of an ITER cooling loop

Fusion Engineering and Design

Volumn 45, Issue 2, 1999, Pages 169-185

  Karditsas, Panos J ^a  

^a CULHAM SCIENCE CENTRE   (United Kingdom)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; CHEMICAL ACTIVATION; COOLING; CORROSION; DOSIMETRY; ESTIMATION; EXPERIMENTAL REACTORS; IONS; NUCLEAR REACTOR LICENSING; RADIOISOTOPES; REACTOR SHUTDOWNS;

FUSION POWER STATIONS; INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR; TRANSPORT ACTIVATION;

FUSION REACTORS;

EID: 0032625003     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(99)00004-6     Document Type: Article

References (18)

1. British Nuclear Energy Society, Proceedings of the 6th International Conference on Water Chemistry of Nuclear Reactor Systems, Bournemouth, UK, 12-15 October, 1992.
2. T. Chandrasekan, et al., Calculation of releases of radioactive material in gaseous and liquid effluents from pressurised water reactors (PWR-GALE code), NUREG-0017, US Nuclear Regulatory Commission, Office of Standards Development (1976).
3. P. Beslu, PACTOLE: a calculational code for predicting corrosion product behaviour and activation in PWR primary coolant systems, CEA Cadarache Report, SCOC/LCC/90-096 (1990).
4. NRC Report, Calculation of releases of radioactive material in gaseous and liquid effluents from boiling water reactors (BWR-GALE code), NUREG-0016, US Nuclear Regulatory Commission, Office of Standards Development (1976).
5. C.C. Baker, et al., STARFIRE-A commercial tokamak fusion power plant study, Argonne National Lab. Report, ANL/FPP-80-1, Appendix G (1980).
6. K.R. Smith, C.B.A. Forty, Estimation of the radioactive content of the primary circuit of a water-cooled fusion reactor and the annual liquid effluent source term, AEA FUS 108 (1991).
7. L. Di Pace, D.G. Cepraga, Evaluation of the activated corrosion products for the ITER heat transfer systems in support of NSSR-1, Report (Rev. 1) ERG-FUS/TECN S+E TR18/96, ENEA, Rome, Italy (1996).
8. G. Saji, Initial activation data for NSSR-l, Report (Rev. 3 - final) D71-07-SEHD-002//D71-07-TSI-001, ITER San Diego JCT, San Diego, USA (1996).
9. Sweeton F.H., Baes C.F. The solubility of magnetite and hydrolysis of ferrous ions in aqueous solutions at elevated temperatures. J. Chem. Thermodyn. 2:1970;479-500.
10. V. Belous, et al., Assessment of the corrosion behaviour of structural materials in the water coolant of ITER, ICFRM-8, Sendai, Japan (1997).
11. J. Kopecky, D. Nierop, The European activation file EAF-4, Petten Report ECN-C-95-072, in preparation.
12. J.F. Briesmeister (Ed.), MCNP - A general Monte Carlo code for neutron and photon transport, Los Alamos Report No, LA-73396-M, Rev. 2 (1986).
13. C.B.A. Forty, Gamma radiation fields around the cooling circuits of a fusion power plant, UKAEA FUS 325, Culham, Abingdon, UK (1996).
14. ICRP, Recommendations of the International Commission on Radiological Protection, Publication 60. Ann. ICRP 21, Pergamon Press, Oxford, UK, 1991.
15. S. Sandri, Radiation personnel safety at PHTS, ERG-FUS/TECN S+E 13/95, (1995).
16. L. Di Pace, et al., Activated corrosion products in ITER first wall and shielding blanket heat transfer system, Proceedings of the 16th SOFE, Champaign, Illinois, USA, 30 September-5 October, 1995, pp. 297-300.
17. C.B.A. Forty, P.J. Karditsas, Preliminary cooling circuit activation and ORE assessment for ITER, Proceedings of the 19th SOFT, Lisbon, Portugal, 16-20 September, 1996, pp. 1835-1838.
18. C.G. Kinniburgh, Occupational radiation exposure, Report SEAFP/R-AlOB (94), (1994).