Reactor Dosimetry Applications Using Raptor-m3g: a New Parallel 3-d Radiation Transport Code
نویسندگان
چکیده
The numerical solution of the Linearized Boltzmann Equation (LBE) via the Discrete Ordinates method (SN) requires extensive computational resources for large 3-D neutron and gamma transport applications due to the concurrent discretization of the angular, spatial, and energy domains. This paper will discuss the development RAPTOR-M3G (RApid Parallel Transport Of Radiation – Multiple 3D Geometries), a new 3-D parallel radiation transport code, and its application to the calculation of ex-vessel neutron dosimetry responses in the cavity of a commercial 2-loop Pressurized Water Reactor (PWR). RAPTOR-M3G is based domain decomposition algorithms, where the spatial and angular domains are allocated and processed on multi-processor computer architectures. As compared to traditional single-processor applications, this approach reduces the computational load as well as the memory requirement per processor, yielding an efficient solution methodology for large 3-D problems. Measured neutron dosimetry responses in the reactor cavity air gap will be compared to the RAPTOR-M3G predictions. This paper is organized as follows: Section 1 discusses the RAPTOR-M3G methodology; Section 2 describes the 2-loop PWR model and the numerical results obtained. Section 3 addresses the parallel performance of the code, and Section 4 concludes this paper with final remarks and future work.
منابع مشابه
Dosimetry at the Portuguese research reactor using thermoluminescence measurements and Monte Carlo calculations.
This work presents an extensive study on Monte Carlo radiation transport simulation and thermoluminescent (TL) dosimetry for characterising mixed radiation fields (neutrons and photons) occurring in nuclear reactors. The feasibility of these methods is investigated for radiation fields at various locations of the Portuguese Research Reactor (RPI). The performance of the approaches developed in ...
متن کاملApplication 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 کاملModeling the measurement of VVER-1000 reactor power by neutron and gamma radiation with MCNP code
The present study deals with a new method for measuring the power of a reactor. This method uses gamma and neutron radiation resulted from the entire reactor structure, without changing its structure (online). In terms of functionality, this method can measure the reactor power in real-time and report it instantly. In order to obtain the relationship between reactor power and gamma and neutron ...
متن کاملParallelization of the Penelope Monte Carlo Particle Transport Simulation Package
We have parallelized the PENELOPE Monte Carlo particle transport simulation package [1]. The motivation is to increase efficiency of Monte Carlo simulations for medical applications. Our parallelization is based on the standard MPI message passing interface. The parallel code is especially suitable for a distributed memory environment, and has been run on up to 256 processors on the Indiana Uni...
متن کاملStatus of Archer — a Monte Carlo Code for the High-performance Heterogeneous Platforms Involving Gpu and Mic
Accelerators such as Graphics Processing Units (GPUs) and Many Integrated Core (MIC) coprocessors are advanced computing devices with outstandingly high computing performance and energy efficiency. The Monte Carlo transport simulation community views these advanced devices as an opportunity to effectively reduce the computation time for performance-critical applications. In this paper, we repor...
متن کامل