Application of IRDF2002 dosimetry data to shielding benchmarks using the Monte Carlo code MCBEND

نویسندگان

  • G. A. Wright
  • C. J. Dean
چکیده

The IRDF2002 dosimetry cross-section data are processed into very fine energy groups and added to the detector response library for the Monte Carlo code MCBEND. The IRDF2002 covariances are processed into broad groups to form a MCBEND detector covariance library. A number of benchmark experiments are analysed using MCBEND with both IRDF2002 and IRDF90 data and the results compared. Uncertainties due to material and detector cross-sections are calculated automatically. The results demonstrate that the IRDF2002 In(n,n')In dosimetry cross-sections give improved agreement between calculation and measurement in an iron benchmark and that use of IRDF2002 data allows straightforward, explicit and accurate calculation of single resonance detector reaction-rates, e.g. Au(n,γ)Au.

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Release of Mcbend 11

MCBEND 11 is the latest version of the general radiation transport Monte Carlo code from AMEC’s ANSWERS Software Service. MCBEND is well-established in the UK shielding community for radiation shielding and dosimetry assessments. Many important developments have been made available to users in this latest release of MCBEND, some of which are described in this paper, including: Geometry Modellin...

متن کامل

Application of MCNP4C Monte Carlo code in radiation dosimetry in heterogeneous phantom

Background: In treating patients with radiation, the degree of accuracy for the delivery of tumor dose is recommended to be within ± 5% by ICRU in report 24. The experimental studies have shown that the presence of low-density inhomogeneity in areas such as the lung can lead to a greater than 30% change in the water dose data. Therefore, inhomogeneity corrections should be used in treatment pla...

متن کامل

A Monte Carlo Study on the Shielding Properties of a Novel Polyvinyl Alcohol (PVA)/WO3 Composite, Against Gamma Rays, Using the MCNPX Code

Background: In recent years, there has been an increased interest toward non-lead radiation shields consisting of small-sized filler particles doped into polymer matrices. In this paper, we study a new polyvinyl alcohol (PVA)/WO3 composite in the presence of high-energy gamma photons through simulation via the Monte Carlo N-Particle (MCNP) simulation code. Materia...

متن کامل

Siemens primus accelerator simulation using EGSnrc Monte Carlo code and gel dosimetry validation with optical computed tomography system by EGSnrc code

Monte Carlo method is the most accurate method for simulation of radiation therapy equipment. The linear accelerators (linac) are currently the most widely used machines in radiation therapy centers. Monte Carlo modeling of the Siemens Primus linear accelerator in 6 MeV beams was used. Square field size of 10 × 10 cm2 produced by the jaws was compared with TLD. Head simulation of Siemens accele...

متن کامل

Monte Carlo calculation of shielding parameters for fast neutrons in newly developed heavy concretes

Introduction: The role of radiotherapy as a part of cancer management increases every year around the world. Thus, Radiation protection in the design of radiotherapy rooms are of great importance.   Materials and Methods: In present study using Monte Carlo method, MCNPX code, fourteen types of developed high density concretes with densities ranging from 2.45 ...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2007