Shane R. Gardner

Pennsylvania State University

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A.D. Carlson

Brookhaven National Laboratory

S. M. Grimes

Ohio University

T. N. Massey

Ohio University

Alireza Haghighat

Virginia Tech

Apisit Patchimpattapong

Electricity Generating Authority of Thailand

James M. Adams

National Institute of Standards and Technology

Michael T. Wenner

University of Florida

Vefa Kucukboyaci

Westinghouse Electric (Japan)

A. Haghighat

Shiraz University

James Adams

Jefferson Community and Technical College

Cooperative Institutions

Pennsylvania State University

University of Florida

Ohio University

Lawrence Livermore National Laboratory

National Institute of Standards and Technology

University of Notre Dame

Fraunhofer Institute for Telecommunications, Heinrich Hertz Institute

NIST Center for Neutron Research

National Institute of Standards

Electricity Generating Authority of Thailand

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Final Report - Novel investigation of iron cross sections via spherical shell transmission measurements and particle transport calculations for material embrittlement studies.

S. M. Grimes T. N. Massey A.D. Carlson James M. Adams Alireza Haghighat

OAK B204 We have been pursuing a multi-year project, funded by the U.S. Department of Energy, to study neutron scattering interactions in iron. The principal objective of this work is to investigate the well-known deficiency that exists for reactor pressure vessel neutron fluence determinations. Specifically, we are using the spherical-shell transmission method, employing iron shells with different thicknesses, and neutron time-of-flight (TOF) measurements of the scattered neutrons, in an effort to precisely determine specific energy regions over which deficiencies in the non-elastic scattering cross section for neutron scattering in iron appear to exist.

Embrittlement

Spherical shell

Neutron Transport

Particle (ecology)

10.2172/810274

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New Particle Transport Methods for Design and Optimization of Spherical-Shell Transmission Measurements

Journal of Nuclear Science and Technology (2002)

Alireza Haghighat Shane R. Gardner Vefa Kucukboyaci Michael T. Wenner James M. Adams

This paper discusses new particle transport methods developed for accurate investigation of iron non-elastic scattering cross sections using the spherical-shell transmission method, employing iron shells with different thicknesses, and neutron time-of-flight spectroscopy of the scattered neutrons. New calculational techniques based on the deterministic and Monte Carlo methods have been developed for design and optimization of the experiment, and for identification and reduction of experimental uncertainties. The new methods include a new tallying option for the MCNP code and new quadrature sets for the 3-D parallel Sn code PENTRAN. The new tallying option is used to determine the optimum source energy versus target thickness, and among the new quadrature sets, the Pn-Tn with ordinate-splitting technique has resulted in accurate flux distributions as compared to Monte Carlo prediction.

Neutron Transport

10.1080/00223131.2002.10875274

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A New Monte Carlo Tallying Methodology for Optimizing the NERI Spherical-Shell Transmission Experiment

Transactions of the American Nuclear Society (2001)

Shane R. Gardner Alireza Haghighat Apisit Patchimpattapong James Adams A.D. Carlson

Spherical shell

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A New Investigation of Iron Cross Sections via Spherical-Shell Transmission Measurements and Particle Transport Calculations

Journal of Nuclear Science and Technology (2002)

James M. Adams Arzu Alpan A.D. Carlson Shane R. Gardner S. M. Grimes

We are engaged in a multi-year project to study neutron scattering interactions in iron, the principal objective of which is to investigate the well-known deficiency that exists in reactor pressure vessel neutron fluence determinations. Specifically, we are using the spherical-shell transmission method, employing iron shells with different thicknesses, and neutron time-of-flight measurements of the scattered neutrons, in an effort to precisely determine specific energy regions over which deficiencies in the non-elastic scattering cross section for neutron scattering in iron appear to exist. The analysis of the experimental data involves correlating the data with theoretical calculations of neutron transport through the iron spheres in order to evaluate the degree to which the calculated neutron spectra predict the measured spectra relative to different types of particle interactions. In doing so, we have developed new methodologies for performing neutron transport calculations that will be useful to a range of transport problems. Preliminary results show good agreement between the experimental data and the calculated distribution of neutron flight times over much of the data range, except for the contribution due to breakup neutrons.

Neutron Transport

10.1080/00223131.2002.10875242

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A New Monte Carlo Tallying Methodology for Optimizing the Nuclear Energy Research Initiative Spherical-Shell Transmission Experiment

Shane R. Gardner A. Haghighat Apisit Patchimpattapong James M. Adams A.D. Carlson

The development of a new tallying methodology for use with the MCNP Monte Carlo particle transport code is reported. The objective is to be able to determine with accuracy the iron nonelastic scattering cross sections via a spherical-shell transmission experiment using the time-of-flight (TOF) method. Different source energy and shell thickness combinations are examined. The actual transmission experiment and the new tallying algorithm are described, and the verification of the new tallying algorithm and its utilization to optimize a neutron TOF experiment are discussed. The results of the work will be used to alleviate the well-known deficiency that exists in the iron nonelastic scattering cross section and thereby reduce the uncertainty in calculations involving deep penetration in iron, e.g. reactor pressure vessel neutron fluence determinations.

Neutron Transport

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Source Initialization of the Monte Carlo Criticality Calculation via Discrete Ordinates (S{sub n}) Methods

Michael T. Wenner Alireza Haghighat Shane R. Gardner

A methodology to use the solution of a deterministic multigroup S{sub n} transport code as the source distribution for a Monte Carlo criticality calculation is discussed. This methodology is referred to as the S{sub n} Source Initialization method. The effectiveness of this methodology is measured by simulating a loosely coupled benchmark, where standard Monte Carlo codes have shown a bias. The Monte Carlo N-Particle transport code MCNP and PENTRAN (three-dimensional parallel, multigroup, S{sub n}) transport code system were used. The PENTRAN code solution is used as a starting source distribution in the MCNP code, thereby decreasing the necessary active cycle length. The methodology was verified on the basis of a sample benchmark problem of a lattice of 5x5x1 highly enriched uranium metal spheres surrounded by air.

Initialization

Neutron Transport

Benchmark (surveying)

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Monte Carlo Analysis of the Spherical Shell Transmission Experiment with New Tallying Methodology

Shane R. Gardner A. Haghighat Apisit Patchimpattapong James Adams A.D. Carlson

This paper discusses a new tallying methodology implemented in the Monte Carlo particle transport code MCNP for tallying a group of particles that are scattered (inelastically and elastically) in a particular region of interest and are detected at a detector. The methodology provides detailed information on the particle’s energy and position. This new tally procedure has been applied to an iron, spherical-shell transmission experiment (SST) to better optimize the experimental setup. The new tallying option is used to identify particles that scattered in the iron shell and subsequently are detected at a detector. The effect of the size and location of the iron shell are analyzed. Various source energies and iron shell thickness are investigated. Note that this new tally methodology can be used in conjunction with any Monte Carlo simulation that requires such information.

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