SESAME: A software tool for the numerical dosimetric reconstruction of radiological accidents involving external sources and its application to the accident in Chile in December 2005

Health Physics

Volumn 96, Issue 1, 2009, Pages 76-83

  Huet, Christelle ^a   Lemosquet, A ^b   Clairand, I ^b   Rioual, J B ^b   Franck, D ^b   De Carlan, L ^b   Aubineau Laniece I ^b   Bottollier Depois, J F ^a  

^a INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

^b NONE

Author keywords

Computer calculations; Dose reconstruction; Dosimetry, external; Phantom

Indexed keywords

ARTICLE; CHILE; COMPUTER PROGRAM; DOSIMETRY; PRIORITY JOURNAL; RADIATION ACCIDENT; RADIATION DOSE DISTRIBUTION; COMPUTER INTERFACE; HUMAN; IMAGE QUALITY; METHODOLOGY; NUCLEAR ACCIDENT; PHOTON; RADIATION DOSE; RADIOMETRY; REPRODUCIBILITY;

CHILE; HUMANS; PHANTOMS, IMAGING; PHOTONS; RADIATION DOSAGE; RADIOACTIVE HAZARD RELEASE; RADIOMETRY; REPRODUCIBILITY OF RESULTS; SOFTWARE; USER-COMPUTER INTERFACE;

EID: 58149392241     PISSN: 00179078     EISSN: None     Source Type: Journal    
DOI: 10.1097/01.HP.0000327661.90794.0f     Document Type: Article

References (13)

1. Borissov N, Franck D, de Carlan L, Laval L. A new graphical user interface for fast construction of computation phantoms and MCNP calculations: application to calibration of in vivo measurement system. Health Phys 83:272-279; 2002. (Pubitemid 34764996)
2. Bottollier-Depois J-F, Gaillard-Lecanu E, Chau Q, Roux A, Trompier F. New approach for dose reconstruction: application to one case of localized irradiation with radiological burns. Health Phys 79:251-256; 2000. (Pubitemid 30643630)
3. Briesmeister JF. MCNP™ - a general Monte Carlo N-particle transport code, version 4B. Los Alamos, NM: Los Alamos National Laboratory; Report LA-12625-M; 1997.
4. Briesmeister JF. MCNP - a general Monte Carlo N-particle transport code, version 4C. Los Alamos, NM: Los Alamos National Laboratory; Report LA-13709-M; 2000.
5. Clairand I, Trompier F, Bottollier-Depois J-F, Gourmelon P. Ex vivo ESR measurements associated with Monte Carlo calculations for accident dosimetry: application to the 2001 Georgian accident. Radiat Protect Dosim 120:500-505; 2006.
6. Cristy M, Eckerman KF. Specific absorbed fractions of energy at various ages from internal photon sources. I. Methods. Oak Ridge, TN: Report Health and Safety Research Division of Oak Ridge National Laboratory; TM-8381/V1; 1987.
7. International Atomic Energy Agency. The radiological accident in Yanango. Vienna: IAEA; 2000a.
8. International Atomic Energy Agency. The radiological accident in Lilo. Vienna: IAEA; 2000b.
9. Lemosquet A, de Carlan L, Clairand I. Voxel anthropomorphic phantoms: review of models used for ionising radiation dosimetry. Radioprotection 38:509-528; 2003.
10. Lemosquet A, Clairand I, de Carlan L, Franck D, Aubineau-Lanièce I, Bottollier-Depois J-F. A computational tool based on voxel geometry for dose reconstruction of a radiological accident due to external exposure. Radiat Protect Dosim 110:449-454; 2004. (Pubitemid 39276778)
11. Roux A, Bottollier-Depois J-F, Gaillard-Lecanu E, Chau Q, Trompier F. Qualifying numerical tools for reconstructing physical doses in the case of accidental exposure to ionising radiation. Radiat Protect Dosim 87:243-249; 2000. (Pubitemid 30216945)
12. Waters LM. MCNPX user's manual, version 2.3.0. Los Alamos, NM: Los Alamos National Laboratory; Report LA-UR-02-2607; 2002a.
13. Waters LM. MCNPX user's manual, version 2.4.0. Los Alamos, NM: Los Alamos National Laboratory; Report LA-CP-02-408; 2002b.