In this paper we give an analysis of the neutron transmission through iron sphere using Monte Carlo and transport theory methods based on ENDF/B-VII.1 general purpose library. The motivation for investigation comes from a well-known deficiency in inelastic data older library evaluation (ENDF/B-V), giving concern fast flux underestimation within reactor pressure vessels. order to benchmark next-...

This paper summarizes the results obtained from an international comparison exercise on neutron spectra unfolding in Bonner spheres spectrometry, organized within activities of EURADOS working group 6: computational dosimetry. Four realistic situations were considered: a medical accelerator, workplace field, irradiation room and skyshine scenario. The reference solutions are presented, given te...

The use of calculated dosimetry metrics is a crucial element in predicting neutron damage to modern semiconductors under various conditions, e.g., control electronics avionic systems, satellite sensors, or power output from solar panels. These have little value unless they are accompanied by quantified uncertainty. This paper outlines mathematical framework that captures the response models for...

Incomplete radiation exposure histories, inadequate treatment of internally deposited radionuclides, and failure to account for neutron exposures can be important uncertainties in epidemiologic studies of radiation workers. Organ-specific doses from lifetime occupational exposures and radionuclide intakes were estimated for an epidemiologic study of 5,801 Rocketdyne/Atomics International (AI) r...

The nuclear safety requirements and philosophy have changed by the development of new nuclear systems and this imposes special research and development activity. Reactor dosimetry which is applied for determination of neutron field parameters and neutron flux responses in different regions of the reactor system plays an important role in determining of radiation exposure on reactor system eleme...

The cross section is a fundamental quantity which affects the accuracy of Monte Carlo simulations widely used in nuclear applications. A new dosimetry library IRDFF-II that contains evaluations include full uncertainty quantification being developed by International Atomic Energy Agency and expected to be released January 2020; preliminary version IRDFF-1.05 was 2014 tested this work. Validatio...

abstract background: with respect to the difference in the interaction of thermal neutron and x rays with matter, using two radiography systems of thermal neutron and x rays will yield highly valuable information for studying the inner structure of biologic samples. methods: the high sensitivity of thermal neutron to hydrogen, in particular, has led to recognizing this system as a useful tool i...