Results 41 to 50 of about 15,370 (183)

Determination of neutron spectrum parameters at IREN facility using the MCNP simulation and experimental validation [PDF]

Nuclear Technology and Radiation Protection
The determination of the characteristics of neutron spectrum at different irradiation positions on the outer wall of moderator chamber of the intense resonance neutron source by simulation method using MCNP code was presented.
Nhat Le Tran Minh, Cong Vu Duc, Khiem Le Hong, Dinh Nguyen Thi, Thanh Pham Tien, Phi Truong Hoai Bao, Thai Nguyen Thi Xuan, Toan Tran Ngoc, Trung Dinh Van, Binh Nguyen Thanh, Son Nguyen An, Shetsov Valery Nikolaevich, Dmitriev Andrey Yuryevich, Lobachev Valerij Vladimirovich, Borzakov Sergey Borisovich   +14 more
doaj   +1 more source

تعیین ویژگیهای دزیمتری چشمه‌های براکی‌تراپی کم انرژی بر اساس دستور کارTG- 43U1 با روشهای مختلف محاسبه دز در کد MCNP [PDF]

مجله علوم و فنون هسته‌ای, 2005
مرکز تحقیقات کشاورزی و پزشکی هسته‌ای سازمان انرژی اتمی ایران، با توجّه به کاربرد روزافزون چشمه‌های کم انرژی I125و Pd103در براکی‌تراپی سرطان پروستات، ساخت اینگونه چشمه‌ها را در دستور کار خود قرار داده است. لذا در این تحقیق بر آن شدیم تا با محاسبات دزیمتری
غلامرضا رئیس علی, فریبا مخلص گرامی, رضا خدادادی, بهناز پیروزفر   +3 more
doaj  

Calculation of Dose Distribution in Neutron Brachytherapy Using 252-Cf Source Through the Monte Carlo Simulation and Comparison with Experimental Data [PDF]

مجله علوم و فنون هسته‌ای, 2018
Detailed recognition of dose distribution around the brachytherapy sources in order to create appropriate plans for treatment of cancer is very important.
Gh Izadi Vasafi, M. M Firoozabadi, I Jabari   +2 more
doaj   +1 more source

Neutron Energy Spectrum Measurements with a Compact Liquid Scintillation Detector on EAST

, 2013
A neutron detector based on EJ301 liquid scintillator has been employed at EAST to measure the neutron energy spectrum for D-D fusion plasma. The detector was carefully characterized in different quasi-monoenergetic neutron fields generated by a 4.5 MV ...
Chen, Jinxiang, Chen, Zhongjing, Fan, Tieshuan, Gorini, G., Hu, Liqun, Peng, Xingyu, Wan, Baonian, Xie, Xufei, Yuan, Xi, Zhang, Guohui, Zhang, Xing, Zhong, Guoqiang   +11 more
core   +1 more source

Maxwell Spectrum as a Parameter to Verify the Dose in Brain Cancer (Glioblastoma) by Boron Neutron Capture Therapy (BNCT) using Monte Carlo Method

Brazilian Journal of Radiation Sciences
To evaluate the efficiency of neutron capture therapy (BNCT) treatment in glioblastoma multiforme, it is necessary to evaluate the impact of the neutron beam on the tumor cell and find better results so that BNCT treatment is viable.
Otto Haubrich, Domingos D'Oliveira Cardoso, Marcos Paulo Cavaliere de Medeiros   +2 more
doaj   +1 more source

بررسی تأثیر نوع آلیاژ آلومینیوم بکار رفته در دیواره اتاقک یونش چاهکدار مرتبط با هوای آزاد بر پاسخ اتاقک در انرژی پرتوهای گامای Cs137، Co57 و Am241 [PDF]

مجله علوم و فنون هسته‌ای, 2007
اتاقک‌های یونش چاهکدار مرتبط با هوای آزاد در مراکز پرتو درمانی برای اندازه‌گیری شدت چشمه‌های براکی تراپی به کار می‌روند. در این کار پژوهشی با استفاده از کد مونت کارلوی MCNP-4C، اتاقک یونش چاهکدار مدل HDR-33004 شبیه‌سازی شده است.
غلامرضا رئیس علی, معصومه دهقانی مقدم, سعید حمیدی, مصطفی غفوری, عبدالرضا سلیمانیان, ارژنگ شاهور, کوروش اربابی   +6 more
doaj  

MCNP: Photon benchmark problems [PDF]

, 1991
The recent widespread, markedly increased use of radiation transport codes has produced greater user and institutional demand for assurance that such codes give correct results. Responding to these pressing requirements for code validation, the general purpose Monte Carlo transport code MCNP has been tested on six different photon problem families ...
Whalen, Daniel J., Hollowell, David E., Hendricks, John S.   +2 more
openaire   +2 more sources

Correlated Prompt Fission Data in Transport Simulations

, 2018
Detailed information on the fission process can be inferred from the observation, modeling and theoretical understanding of prompt fission neutron and $\gamma$-ray~observables. Beyond simple average quantities, the study of distributions and correlations
Andrews, M. T., Clarke, S. D., Jaffke, P., Jandel, M., Kawano, T., Marcath, M. J., Meierbachtol, K., Nakae, L., Pozzi, S. A., Randrup, J., Rising, M. E., Rusev, G., Sood, A., Stetcu, I., Talou, P., Verbeke, J., Vogt, R., Walker, C.   +17 more
core   +1 more source

Neutron Activation and Layout Optimization Experiments by MCNP Code for the Main Elements of Cement [PDF]

مجله علوم و فنون هسته‌ای, 2016
Iran is the fourth largest cement producing country in the world, and one of the pioneers in this industry. For this reason, study and further research in the fields related to the cement industry are of great importance.
S.A. Safari, S. A Moussavi Zarandi, A Jafari   +2 more
doaj  

Numerical simulation and experimental study of PbWO4/EPDM and Bi2WO6/EPDM for the shielding of {\gamma}rays

, 2016
The MCNP5 code was employed to simulate the {\gamma}ray shielding capacity of tungstate composites. The experimental results were applied to verify the applicability of the Monte Carlo program.
Li, Yingjun, Li, Yintao, Song, Chi, Zhang, Quanping, Zheng, Jian, Zhou, Yuanlin   +5 more
core   +1 more source