skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: TRACKING CHARGED PARTICLES THROUGH MAGNETIC FIELDS USING MCNP AND MCNPX

Abstract

No abstract prepared.

Authors:
; ;
Publication Date:
Research Org.:
Los Alamos National Lab., NM (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
785028
Report Number(s):
LA-UR-99-2809
TRN: US0111265
DOE Contract Number:
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: Conference title not supplied, Conference location not supplied, Conference dates not supplied; Other Information: PBD: 1 Nov 1999
Country of Publication:
United States
Language:
English
Subject:
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; CHARGED PARTICLES; MAGNETIC FIELDS; PARTICLE TRACKS; MONTE CARLO METHOD; RADIATION TRANSPORT

Citation Formats

J. A. FAVORITE, K. ADAMA, and J. ZUMBRO. TRACKING CHARGED PARTICLES THROUGH MAGNETIC FIELDS USING MCNP AND MCNPX. United States: N. p., 1999. Web.
J. A. FAVORITE, K. ADAMA, & J. ZUMBRO. TRACKING CHARGED PARTICLES THROUGH MAGNETIC FIELDS USING MCNP AND MCNPX. United States.
J. A. FAVORITE, K. ADAMA, and J. ZUMBRO. 1999. "TRACKING CHARGED PARTICLES THROUGH MAGNETIC FIELDS USING MCNP AND MCNPX". United States. doi:. https://www.osti.gov/servlets/purl/785028.
@article{osti_785028,
title = {TRACKING CHARGED PARTICLES THROUGH MAGNETIC FIELDS USING MCNP AND MCNPX},
author = {J. A. FAVORITE and K. ADAMA and J. ZUMBRO},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1999,
month =
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share:
  • The MCNP and MCNPX multiparticle Monte Carlo transport codes have been modified with a patch that allows specialized tracking of charged particles through the magnetic fields of a charged-particle beam optics system using pregenerated maps output from the COSY INFINITY code. A map is the rule for updating the particles' phase-space through a magnetic element. A file containing a single COSY map is assigned to each magnetic cell, which must be a vacuum. For current applications, the COSY maps are generated for protons, but any charged particle will be properly transported.
  • The MCNP code is written and maintained by Group X-TM at Los Alamos National Laboratory. In response to the demands of the accelerator community, the authors have undertaken a major effort to expand the capabilities of MCNP to increase the set of transportable particles; to make use of newly evaluated high-energy nuclear data tables for neutrons, protons, and potentially other particles; and to incorporate physics models for use where tabular data are unavailable. A preliminary version of the expanded code, called MCNPX, has now been issued for testing. The new code includes all existing LAHET physics modules, and has themore » ability to utilize the 150-MeV data libraries that have recently been released by LANL Group T-2.« less
  • An LDRD (Laboratory Directed Research and Development) project is underway at the Idaho National Laboratory (INL) to apply the three-dimensional multi-group deterministic neutron transport code (Attila®) to criticality, flux and depletion calculations of the Advanced Test Reactor (ATR). This paper discusses the development of Attila models for ATR, capabilities of Attila, the generation and use of different cross-section libraries, and comparisons to ATR data, MCNP, MCNPX and future applications.
  • The 3D neutron transport code Attila{sup R} has been used in a Laboratory Directed Research and Development (LDRD) project for the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). The purpose is to examine the feasibility of replacing the current diffusion based Core Safety Analysis Methods with a neutron transport code. This is a discussion of the development of the Attila models, and their comparison to models from other codes and historical data from the ATR. Additional comparisons have been made to the ATR Critical Facility (ATRC), the low power version of ATR, used for physics testing. (authors)
  • Purpose: The purpose of this study was to compare and validate three methods to simulate radiographic image detectors with the Monte Carlo software MCNP/MCNPX in a time efficient way. Methods: The first detector model was the standard semideterministic radiography tally, which has been used in previous image simulation studies. Next to the radiography tally two alternative stochastic detector models were developed: A perfect energy integrating detector and a detector based on the energy absorbed in the detector material. Validation of three image detector models was performed by comparing calculated scatter-to-primary ratios (SPRs) with the published and experimentally acquired SPR values.more » Results: For mammographic applications, SPRs computed with the radiography tally were up to 44% larger than the published results, while the SPRs computed with the perfect energy integrating detectors and the blur-free absorbed energy detector model were, on the average, 0.3% (ranging from -3% to 3%) and 0.4% (ranging from -5% to 5%) lower, respectively. For general radiography applications, the radiography tally overestimated the measured SPR by as much as 46%. The SPRs calculated with the perfect energy integrating detectors were, on the average, 4.7% (ranging from -5.3% to -4%) lower than the measured SPRs, whereas for the blur-free absorbed energy detector model, the calculated SPRs were, on the average, 1.3% (ranging from -0.1% to 2.4%) larger than the measured SPRs. Conclusions: For mammographic applications, both the perfect energy integrating detector model and the blur-free energy absorbing detector model can be used to simulate image detectors, whereas for conventional x-ray imaging using higher energies, the blur-free energy absorbing detector model is the most appropriate image detector model. The radiography tally overestimates the scattered part and should therefore not be used to simulate radiographic image detectors.« less