These tools will no longer be maintained as of December 31, 2024. Archived website can be found here. PubMed4Hh GitHub repository can be found here. Contact NLM Customer Service if you have questions.


BIOMARKERS

Molecular Biopsy of Human Tumors

- a resource for Precision Medicine *

119 related articles for article (PubMed ID: 12362914)

  • 1. Monte carlo simulations and experimental studies of yttrium-90 production using a 33 MeV linac.
    Necsoiu D; Morgan IL; Hupf H; Courtney WJ; Kinross-Wright J; El Bouanani M; Duggan JL; McDaniel FD
    Appl Radiat Isot; 2002 Oct; 57(4):509-15. PubMed ID: 12362914
    [TBL] [Abstract][Full Text] [Related]  

  • 2. Photonuclear dose calculations for high-energy photon beams from Siemens and Varian linacs.
    Chibani O; Ma CM
    Med Phys; 2003 Aug; 30(8):1990-2000. PubMed ID: 12945965
    [TBL] [Abstract][Full Text] [Related]  

  • 3. Modeling and experimental data of zirconium-89 production yield.
    Sharifian M; Sadeghi M; Alirezapour B; Yarmohammadi M; Ardaneh K
    Appl Radiat Isot; 2017 Dec; 130():206-210. PubMed ID: 28992565
    [TBL] [Abstract][Full Text] [Related]  

  • 4. A scintillator-based approach to monitor secondary neutron production during proton therapy.
    Clarke SD; Pryser E; Wieger BM; Pozzi SA; Haelg RA; Bashkirov VA; Schulte RW
    Med Phys; 2016 Nov; 43(11):5915. PubMed ID: 27806590
    [TBL] [Abstract][Full Text] [Related]  

  • 5. Shielding implications for secondary neutrons and photons produced within the patient during IMPT.
    DeMarco J; Kupelian P; Santhanam A; Low D
    Med Phys; 2013 Jul; 40(7):071701. PubMed ID: 23822405
    [TBL] [Abstract][Full Text] [Related]  

  • 6. Dose distributions in a human head phantom for neutron capture therapy using moderated neutrons from the 2.5 meV proton-7Li reaction or from fission of 235U.
    Tanaka K; Kobayashi T; Sakurai Y; Nakagawa Y; Endo S; Hoshi M
    Phys Med Biol; 2001 Oct; 46(10):2681-95. PubMed ID: 11686282
    [TBL] [Abstract][Full Text] [Related]  

  • 7. WENDI: an improved neutron rem meter.
    Olsher RH; Hsu HH; Beverding A; Kleck JH; Casson WH; Vasilik DG; Devine RT
    Health Phys; 2000 Aug; 79(2):170-81. PubMed ID: 10910387
    [TBL] [Abstract][Full Text] [Related]  

  • 8. DETERMINATION OF THE RESPONSE TO THE ATMOSPHERIC COSMIC RADIATION OF A NEUTRON DOSIMETER ASSISTED BY MONTE CARLO SIMULATION.
    Pereira MA; Federico CA; Gonçalez OL
    Radiat Prot Dosimetry; 2018 Oct; 181(2):142-148. PubMed ID: 29378015
    [TBL] [Abstract][Full Text] [Related]  

  • 9. Simulation of neutron production using MCNPX+MCUNED.
    Erhard M; Sauvan P; Nolte R
    Radiat Prot Dosimetry; 2014 Oct; 161(1-4):261-4. PubMed ID: 24132389
    [TBL] [Abstract][Full Text] [Related]  

  • 10. Development of a dual phantom technique for measuring the fast neutron component of dose in boron neutron capture therapy.
    Sakurai Y; Tanaka H; Kondo N; Kinashi Y; Suzuki M; Masunaga S; Ono K; Maruhashi A
    Med Phys; 2015 Nov; 42(11):6651-7. PubMed ID: 26520755
    [TBL] [Abstract][Full Text] [Related]  

  • 11. Estimation of photoneutron yield in linear accelerator with different collimation systems by Geant4 and MCNPX simulation codes.
    Kim YS; Khazaei Z; Ko J; Afarideh H; Ghergherehchi M
    Phys Med Biol; 2016 Apr; 61(7):2762-79. PubMed ID: 26975304
    [TBL] [Abstract][Full Text] [Related]  

  • 12. Empirical description and Monte Carlo simulation of fast neutron pencil beams as basis of a treatment planning system.
    Bourhis-Martin E; Meissner P; Rassow J; Baumhoer W; Schmidt R; Sauerwein W
    Med Phys; 2002 Aug; 29(8):1670-7. PubMed ID: 12201412
    [TBL] [Abstract][Full Text] [Related]  

  • 13. Monte Carlo simulations and experimental results on neutron production in the uranium spallation target QUINTA irradiated with 660 MeV protons.
    Khushvaktov JH; Adam J; Baldin AA; Furman WI; Gustov SA; Kish YV; Solnyshkin AA; Stegailov VI; Svoboda J; Tichy P; Tsoupko-Sitnikov VM; Tyutyunnikov SI; Vespalec R; Vrzalova J; Wagner V; Yuldashev BS; Zavorka L; Zeman M
    Appl Radiat Isot; 2018 Jul; 137():102-107. PubMed ID: 29602028
    [TBL] [Abstract][Full Text] [Related]  

  • 14. Characterization of a high-dose-rate 90Sr-90Y source for intravascular brachytherapy by using the Monte Carlo code PENELOPE.
    Asenjo J; Fernández-Varea JM; Sánchez-Reyes A
    Phys Med Biol; 2002 Mar; 47(5):697-711. PubMed ID: 11931465
    [TBL] [Abstract][Full Text] [Related]  

  • 15. Prediction of 94mTc production for positron emission tomography studies using the Monte Carlo code MCNPX-2.6.
    Sadeghi M; Hashemi N; Afarideh H; Tenreiro C
    Appl Radiat Isot; 2013 Dec; 82():347-50. PubMed ID: 24161593
    [TBL] [Abstract][Full Text] [Related]  

  • 16. Cross section measurements for (n, 3n) reactions induced by 14.8 MeV neutrons.
    Li G; Pu Z; Kong X; Zhang F; Zhu X
    Appl Radiat Isot; 2002 May; 56(5):731-3. PubMed ID: 11993948
    [TBL] [Abstract][Full Text] [Related]  

  • 17. Monte Carlo modeling of proton therapy installations: a global experimental method to validate secondary neutron dose calculations.
    Farah J; Martinetti F; Sayah R; Lacoste V; Donadille L; Trompier F; Nauraye C; De Marzi L; Vabre I; Delacroix S; Hérault J; Clairand I
    Phys Med Biol; 2014 Jun; 59(11):2747-65. PubMed ID: 24800943
    [TBL] [Abstract][Full Text] [Related]  

  • 18. Prediction of neutron induced radioactivity in the concrete walls of a PET cyclotron vault room with MCNPX.
    Martínez-Serrano JJ; Díez de los Ríos A
    Med Phys; 2010 Nov; 37(11):6015-21. PubMed ID: 21158313
    [TBL] [Abstract][Full Text] [Related]  

  • 19. Fast neutron absorbed dose distributions in the energy range 0.5-80 meV--a Monte Carlo study.
    Söderberg J; Carlsson GA
    Phys Med Biol; 2000 Oct; 45(10):2987-3007. PubMed ID: 11049184
    [TBL] [Abstract][Full Text] [Related]  

  • 20. Prediction of 67Ga production using the Monte Carlo code MCNPX.
    Sadeghi M; Jokar N; Kakavand T; Ghafoori Fard H; Tenreiro C
    Appl Radiat Isot; 2013 Jul; 77():14-7. PubMed ID: 23500652
    [TBL] [Abstract][Full Text] [Related]  

    [Next]    [New Search]
    of 6.