邢唷��>� EG��D��欹� ��!bjbj€€€€ *0怅鑏怅鑏� ��hh��8�$�a�9OOOO*"LX��$M!�$��`**``��OO��`��O�O��`��r�Tl��pn擻bW��pP�10a^�$^:�$l�$�l```�`````�```a````��$`````````h s: IRINA I. POPOVA 2221 Villa Garden Way, Knoxville, TN 37932 E-mail: HYPERLINK "mailto:popovai@ornl.gov" popovai@ornl.gov FORMAL EDUCATION: September 1882 - February 1988: M.S. degree in Nuclear Engineering from Moscow Power Engineering University, with specialization in Thermal Analysis and Nuclear Physics. MISCELLANEOUS EDUCATION: 2014: 1 week course: Unstructured mesh generator w/ Attila4MC Training Class, 2005: 1 week course: Radiation Detection and Measurement, 2001: 10 days course: Accelerator Radiation Protection, International School of Radiation Damage and Protection 2000: 1 week MCNPX advanced classes in Oak Ridge. 1999: 12 weeks fellowship for criticality and shielding analysis of spent fuel casks at the 91暗网, USA. Training included the use of ORIGIN-S to generate the source terms for fuel assemblies (PWR, VVER) and the applying MCNP for criticality and shielding calculations. 1998: 3 weeks fellowship on MCU code application for criticality analysis in Kurchatov Institute, Russia. 1995: Attended a short course on Nuclear Physics organized by Institute for Nuclear Research and Nuclear Energy, Varna, Bulgaria. AWARDS: 2003: Significant Event Award by Spallation Neutron Source Project (ORNL) for completion of the Title II Design Reviews for the Target System. 2000: Academicals Award in Physical Science from Bulgarian Academy of Science for the 揇etermination of neutron fluence impact on the reactor core in the Kozloduy Nuclear Power Plant� during period of time: 1995-1999. 1998: Best Paper Award (I.Popova, S.Belousov, K.Ilieva 揤isualisation and Checking of VVER Reactor Geometry Models�) presented for young scientists at the International Annual Meeting of Yugoslavian Nuclear Society. ORGANIZATIONS: American Nuclear Society (present), member of Oak Ridge local section executive committee, member of number of national ANS committees WGRD-VVER (Working Group for Reactor Dosimetry of VVER) (1995-2000), Bulgarian Nuclear Society, Bulgarian Physics Society (1995-2000). Professional Experience: Dec. 2005 � Present: Radiation Protection and Neutronics Support in Neutron Sciences (Instrument and Source Division), 91暗网. Dec. 2001 � 2005: Radiation Protection and Neutronics Support in Spallation Neutron Source Project (Experimental Facility Division), 91暗网. Jan. 2000 � Nov. 2001: Post-grad employment (through ORISE) with the SNS Division at ORNL, to perform shielding and activation analyses for the SNS target group. Aug. 1988 � 1990, 1994 -1999: Nuclear Research fellow in the Neutron Transport group of the Reactor Physics Division of the Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences. Field of Experience: Activation and neutronics analyses to support Proton Power upgrade Waste management analyses for accelerator and target facilities at SNS to support storage and transport containers design for removed irradiated equipment. Conduction implementation of temporary shielding plan after shut downs for facility maintenance. Delayed neutrons studies for mercury target at SNS. Member of Instrument System Safety Committee for SNS (Spallation Neutron Source), which provides an independent evaluation of instruments as they are constructed, commissioned, operated, and modified; and member of Instrument Readiness Review Committee. Transport and activation analyses for SNS to support accelerator facility during operation, using MCNPX, DORT, TORT, ANISN, and transmutation codes such as CINDER. Procedures development for conducting shielding analyses at SNS beam lines. Conducting neutronics analyses and shielding development for SNS beam lines and its detector enclosures. Neutronic and activation analyses for the Spallation Neutron Source at ORNL:(1) shielding analyses for the target system ,(2) radioactive isotope production analyses for environmental safety, radiation field prediction for the project safety and maintenance access planning. Methods, codes and data verification/validation for the high-energy particles accelerator shielding design and neutronic and activation analyses. Conducting neutronic analyses to support shielding development and radiation safety issues for spent fuel casks for storage of VVER power plant type assemblies, mostly with SCALE code system, Criticality analysis of spent fuel casks for transport and storage of VVER power plant type assemblies with world-wide Monte Carlo codes. Prediction of pin power distribution for the real critical experimental assembly. Elaboration of interface software package for preparing and checking the input data for neutron fluence and dosimetry calculations by discrete ordinates transport DORT/TORT codes (Fortran). Development of software interface package for data transmission from reactor core codes output files to input files of discrete ordinate transport code. Preparation of different fixed sources, needed for calculating appropriate responses of the neutron flux: neutron fluence, induced activity and radiation damage dose. Performance of neutron transport modeling for VVER type reactors for estimation of irradiation embrittlement of VVER-440/230 vessel and for neutron exposure evaluation onto VVER-440/1000 RPVs and surveillance, to support nuclear power plant safety. Comparative analyses of benchmarks on neutron transport testing through iron and beryllium slabs and spheres from 14 MeV and fission sources. Multigroup constants' library preparation using ENDF-IV for time of flight (TOF) spectrometer calculations. Recent activity: Spallation Neutron Source at ORNL, neutronics and activation analyses Spallation Neutron Project at ORNL, shielding development. Project sponsored by NRC, USA 揜eactor Vessel Dosimetry Benchmark for Commercial VVER-440 Plants�, May 1996- May 1997. IAEA Regional Project No. RER/4/017 揇atabase for VVER-1000 RPV�, January 1997 - 1998 IAEA Research Contract No. 9734/R0 揅reation of ex-vessel activity detectors� data bank for evaluation of neutron fluence onto VVER-440/230 vessel� October 1997- 1998. IAEA Research Contract No. 8831/R0 揃enchmarks on neutron transport from 14 MeV and fission source for FENDL testing� October 1996- June 1998. Project TACIS SRR 2/95 揇evelopment of advanced methods for the evaluation of irradiation embrittlement of WWER-1000/320 type RPVs.� Dosimetry part., Feb 1998 - 2000. Contracts with Kozloduy NPP for neutron exposure evaluation onto the VVER-440 and VVER-1000 RPVs and surveillances. 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