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410 related items for PubMed ID: 15353719
1. Dosimetry of BNCT beams with novel thermoluminescent detectors. Bilski P, Budzanowski M, Ochab E, Olko P, Czopyk Ł. Radiat Prot Dosimetry; 2004; 110(1-4):623-6. PubMed ID: 15353719 [Abstract] [Full Text] [Related]
2. Study of a method based on TLD detectors for in-phantom dosimetry in BNCT. Gambarini G, Klamert V, Agosteo S, Birattari C, Gay S, Rosi G, Scolari L. Radiat Prot Dosimetry; 2004; 110(1-4):631-6. PubMed ID: 15353721 [Abstract] [Full Text] [Related]
3. Development of a tiny neutron probe with an optical fibre for BNCT. Ito Y, Katano G, Harano H, Matsumoto T, Uritani A, Kudo K, Kobayashi K, Yoshimoto T, Sakurai Y, Kobayashi T, Mori C. Radiat Prot Dosimetry; 2004; 110(1-4):619-22. PubMed ID: 15353718 [Abstract] [Full Text] [Related]
5. Combined TL and 10B-alanine ESR dosimetry for BNCT. Bartolotta A, D'Oca MC, Lo Giudice B, Brai M, Borio R, Forini N, Salvadori P, Manera S. Radiat Prot Dosimetry; 2004; 110(1-4):627-30. PubMed ID: 15353720 [Abstract] [Full Text] [Related]
6. A toolkit for epithermal neutron beam characterisation in BNCT. Auterinen I, Serén T, Uusi-Simola J, Kosunen A, Savolainen S. Radiat Prot Dosimetry; 2004; 110(1-4):587-93. PubMed ID: 15353713 [Abstract] [Full Text] [Related]
8. Alanine and TLD coupled detectors for fast neutron dose measurements in neutron capture therapy (NCT). Cecilia A, Baccaro S, Cemmi A, Colli V, Gambarini G, Rosi G, Scolari L. Radiat Prot Dosimetry; 2004; 110(1-4):637-40. PubMed ID: 15353722 [Abstract] [Full Text] [Related]
9. An accelerator-based epithermal neutron beam design for BNCT and dosimetric evaluation using a voxel head phantom. Lee DJ, Han CY, Park SH, Kim JK. Radiat Prot Dosimetry; 2004; 110(1-4):655-60. PubMed ID: 15353726 [Abstract] [Full Text] [Related]
10. Microdosimetry of neutron field for boron neutron capture therapy at Kyoto university reactor. Endo S, Onizuka Y, Ishikawa M, Takada M, Sakurai Y, Kobayashi T, Tanaka K, Hoshi M, Shizuma K. Radiat Prot Dosimetry; 2004; 110(1-4):641-4. PubMed ID: 15353723 [Abstract] [Full Text] [Related]
11. Characterisation of the TAPIRO BNCT thermal facility. Rosi G, Gambarini G, Colli V, Gay S, Scolari L, Fiorani O, Perrone A, Nava E, Fasolo F, Visca L, Zanini A. Radiat Prot Dosimetry; 2004; 110(1-4):651-4. PubMed ID: 15353725 [Abstract] [Full Text] [Related]
12. Development of a TL detector for neutron measurement by CaSO4:Dy phosphors. Yang JS, Kim JL, Kim DY, Chang SY. Radiat Prot Dosimetry; 2004; 110(1-4):301-4. PubMed ID: 15353663 [Abstract] [Full Text] [Related]
13. BNCT microdosimetry at the tapiro reactor thermal column. De Nardo L, Seravalli E, Rosi G, Esposito J, Colautti P, Conte V, Tornielli G. Radiat Prot Dosimetry; 2004; 110(1-4):579-86. PubMed ID: 15353712 [Abstract] [Full Text] [Related]
14. Dosimetric measurements with a brain equivalent plastic walled ionization chamber in an epithermal neutron beam. Binns PJ, Riley KJ, Harling OK. Radiat Prot Dosimetry; 2004; 110(1-4):687-92. PubMed ID: 15353731 [Abstract] [Full Text] [Related]
15. Application of different TL detectors for the photon dosimetry in mixed radiation fields used for BNCT. Burgkhardt B, Bilski P, Budzanowski M, Böttger R, Eberhardt K, Hampel G, Olko P, Straubing A. Radiat Prot Dosimetry; 2006; 120(1-4):83-6. PubMed ID: 16644976 [Abstract] [Full Text] [Related]
17. Investigations of recombination chambers for BNCT beam dosimetry. Tulik P, Golnik N, Zielczynski M. Radiat Prot Dosimetry; 2007; 126(1-4):648-51. PubMed ID: 17576649 [Abstract] [Full Text] [Related]
18. Recombination chambers filled with different gases--studies of possible application for BNCT beam dosimetry. Tulik P, Golnik N, Zielczynski M. Radiat Prot Dosimetry; 2004; 110(1-4):669-73. PubMed ID: 15353728 [Abstract] [Full Text] [Related]
19. Measurements of gamma dose and thermal neutron fluence in phantoms exposed to a BNCT epithermal beam with TLD-700. Gambarini G, Magni D, Regazzoni V, Borroni M, Carrara M, Pignoli E, Burian J, Marek M, Klupak V, Viererbl L. Radiat Prot Dosimetry; 2014 Oct; 161(1-4):422-7. PubMed ID: 24435913 [Abstract] [Full Text] [Related]
20. Dose calculation in biological samples in a mixed neutron-gamma field at the TRIGA reactor of the University of Mainz. Schmitz T, Blaickner M, Schütz C, Wiehl N, Kratz JV, Bassler N, Holzscheiter MH, Palmans H, Sharpe P, Otto G, Hampel G. Acta Oncol; 2010 Oct; 49(7):1165-9. PubMed ID: 20831509 [Abstract] [Full Text] [Related] Page: [Next] [New Search]