Progress and prospects of calculation methods for radiation shielding

Abstract

Progress in calculation methods for radiation shielding are reviewed based on the activities of research committees related to radiation shielding fields established in the Atomic Energy Society of Japan. A technological roadmap for the field of radiation shielding; progress and prospects for specific shielding calculation methods such as the Monte Carlo, discrete ordinate Sn transport, and simplified methods; and shielding experiments used to validate calculation methods are presented in this paper.

An Accurate and Efficient S N Method for Multigroup Neutron Transport Equations in Slab Geometry

“…They can model neutron behavior in complex reactor geometries, calculate criticality, and optimize reactor performance [5,6,7,8]. In neutron shielding design applications, S N methods are used to design neutron shielding materials and configurations to protect workers and the public from radiation exposure [9,10,11]. In medical physics, S N methods are employed for radiation therapy treatment planning.…”

Finite Element Formulation and Simulation of Gamma Ray Attenuation of Single and Multilayer Materials Using Lead, Tungsten and EPDM

“…Hence radiation shields with adequate attenuation properties are required for protection [1] . In determining the capability of a material to attenuate gamma rays computational methods prove to be an indispensable tool due to the advancement in computer development and hence of high demand [2] . Computer codes based on Discrete Ordinate, Monte Carlo, Finite Element Method and the Points kernel method have been developed.…”

Assessment of Tools for Molten Salt Reactor Dose Rate Calculations

“…The inadequate coarse mesh adopted may also have caused negative fluxes. For designs with large non-scattering regions, the so-called "ray effects" may lead to enhancement of neutron fluxes along the SN angles [2]. For the simplified MSR core, we were not able to successfully within a 2-month period accurately calculate the biological dose rates outside the core where the neutron fluxes are dropped by more than 14 orders of magnitude after passing the thick shielding tank [1].…”