Particle-transport simulation with the Monte Carlo method

Carter, L. L.; Cashwell, E.D.

doi:10.2172/4167844

Cited by 258 publications

(150 citation statements)

References 7 publications

Supporting

Mentioning

147

Contrasting

Unclassified

Order By: Relevance

“…is the inverse wavelength of the recoiling atom: Upon a coherent scattering interaction, the scattering angle cosine is sampled from f coh (E , μ) using the rejection technique method from Carter and Cashwell [11]. A scattering azimuth is selected randomly from [0, 2π].…”

Section: Forwardmentioning

confidence: 99%

See 1 more Smart Citation

Continuous energy adjoint transport for photons in PHITS

2017

View full text Add to dashboard Cite

Abstract. Adjoint Monte Carlo can be an efficient algorithm for solving photon transport problems where the size of the tally is relatively small compared to the source. Such problems are typical in environmental radioactivity calculations, where natural or fallout radionuclides spread over a large area contribute to the air dose rate at a particular location. Moreover photon transport with continuous energy representation is vital for accurately calculating radiation protection quantities. Here we describe the incorporation of an adjoint Monte Carlo capability for continuous energy photon transport into the Particle and Heavy Ion Transport code System (PHITS). An adjoint cross section library for photon interactions was developed based on the JENDL-4.0 library, by adding cross sections for adjoint incoherent scattering and pair production. PHITS reads in the library and implements the adjoint transport algorithm by Hoogenboom. Adjoint pseudo-photons are spawned within the forward tally volume and transported through space. Currently pseudo-photons can undergo coherent and incoherent scattering within the PHITS adjoint function. Photoelectric absorption is treated implicitly. The calculation result is recovered from the pseudo-photon flux calculated over the true source volume. A new adjoint tally function facilitates this conversion. This paper gives an overview of the new function and discusses potential future developments.

show abstract

Section: Forwardmentioning

confidence: 99%

“…Kahn's rejection method is employed for photons below 1.5 MeV [12] and Koblinger's method for E > 1.5 MeV [13], following Blomquist and Gelbard [14]. The candidate is then accepted or rejected against the incoherent scattering function [11]. Note for the calculation of S (Z, x ), Monte Carlo codes (e.g.…”

Section: Forwardmentioning

confidence: 99%

Continuous energy adjoint transport for photons in PHITS

2017

View full text Add to dashboard Cite

show abstract

“…Using the track length estimator method, the group-wise scalar flux within a single region for a single generation of particles is calculated as follows [7,8,9]:…”

Section: Calculation Of Flux Momentsmentioning

confidence: 99%

Sensitivity and Uncertainty Analysis for Nuclear Criticality Safety Using KENO in the SCALE Code System

Rearden

2001

Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications

View full text Add to dashboard Cite

Abstract. Sensitivity and uncertainty methods have been developed to aid in the establishment of areas of applicability and validation of computer codes and nuclear data for nuclear criticality safety studies. A key component in this work is the generation of sensitivity and uncertainty parameters for typically several hundred benchmarks experiments used in validation exercises.Previously, only onedimensional sensitivity tools were available for this task, which necessitated the remodeling of multidimensional inputs in order for such an analysis to be performed. This paper describes the development of the SEN3 Monte Carlo based sensitivity analysis sequence for SCALE.Two options in the SEN3 package for the reconstruction of angular-dependent forward and adjoint fluxes are described and contrasted. These options are the direct calculation of flux moments versus the calculation of angular fluxes, with subsequent conversion to flux moments prior to sensitivity coefficient generation. The latter technique is found to be significantly more efficient.

show abstract

“…In order to model the scattering process, Monte Carlo methods where chosen. The Monte Carlo method is a means of simulating a random process [4]. The Monte Carlo technique used in this program could be termed a brute force method.…”

Section: Modeling Neutron Radiography Neutron Interaction With Mattermentioning

confidence: 99%

“…The x and y coordinates of the scattering site are equal to those of the point detect(X,Y,O). Otherwise if R is greater than the cross-section ratio, the event is an absorption [4,5].…”

Section: Determining Neutron Locationmentioning

confidence: 99%

Development of a Neutron Radiography Simulation Model

Groth

Gray

1993

Review of Progress in Quantitative Nondestructive Evaluation

View full text Add to dashboard Cite

INTRODUCfIONMeasurement models of NDE techniques have been developed with the purpose of proving the capabilities of NDE techniques for finding flaws. The models take NDE parameters such as ultrasonic frequency, probe diameter, and angle of incidence, and predict the response from the flaw. Models are also a part of quantitative NDE, i.e., the ability to size and characterize flaws and or materials.Nondestructive examination techniques should be utilized throughout the life of a component. This use would incorporate NDE into what is known as unified life cycle engineering. Life cycle engineering considers all aspects of a components life in the design process [1]. The starting point for NDE in the life cycle is the procurement of materials and components. Models are used in the design process to determine the inspectability of the fmished component. Another use for models is the choice of NDE technique and the determination of optimum NDE parameters. Also, in-service inspection needs can be addressed by models [2]. Neutron radiography is one of the types of NDE currently practiced. The remainder of this paper will focus on modeling of this method. Conventional Neutron RadiographyCustomary neutron radiography has four essential components. A source of neutrons is needed. This source is usually either a reactor, an accelerator, or a spontaneous neutron source such as californium-252. Since thermal neutrons are used in radiography, the highly energetic neutrons from fission sources must be slowed. The second requirement for neutron radiography is a means of collimating the neutrons from the nonisotropic source into a parallel beam. The third need of neutron radiography is the sample. An example of a legitimate sample for use with neutron radiography would be a part which is being inspected for corrosion. The low Z material in the corrosion is relatively easy to detect with neutron radiography.A method of detection is the final necessity of neutron radiography. The transfer method utilizing an indium foil is commonly employed. The indium foil is placed behind

show abstract

Particle-transport simulation with the Monte Carlo method

Cited by 258 publications

References 7 publications

Continuous energy adjoint transport for photons in PHITS

Continuous energy adjoint transport for photons in PHITS

Sensitivity and Uncertainty Analysis for Nuclear Criticality Safety Using KENO in the SCALE Code System

Development of a Neutron Radiography Simulation Model

Contact Info

Product

Resources

About