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in creator/contributor: "Fu, C.Y."

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Intelligent Signal Processing for Detection System Optimization

A wavelet-neural network signal processing method has demonstrated approximately tenfold improvement over traditional signal-processing methods for the detection limit of various nitrogen and phosphorus compounds from the output of a thermionic detector attached to a gas chromatograph. A blind test was conducted to validate the lower detection limit. All fourteen of the compound spikes were detected when above the estimated threshold, including all three within a factor of two above the thresho… more

Date: December 5, 2004

Creator: Fu, C. Y.; Petrich, L. I.; Daley, P. F. & Burnham, A. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Intelligent Signal Processing for Detection System Optimization

A wavelet-neural network signal processing method has demonstrated approximately tenfold improvement in the detection limit of various nitrogen and phosphorus compounds over traditional signal-processing methods in analyzing the output of a thermionic detector attached to the output of a gas chromatograph. A blind test was conducted to validate the lower detection limit. All fourteen of the compound spikes were detected when above the estimated threshold, including all three within a factor of … more

Date: June 18, 2004

Creator: Fu, C Y; Petrich, L I; Daley, P F & Burnham, A K

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Combining Semi-Classical and Quantum Mechanical Methodologies for Nuclear Cross-section Calculations Between 1 Mev and 5 Gev

With a goal to develop a nuclear cross-section code usable over the wide energy range of 1 MeV to 5 GeV, one option is to combine intranuclear cascade, pre-equilibrium, and Hauser-Feshbach models in existing codes. However, the first two models are semi-classical while the third one is quantum mechanical, and combining them is not straightforward because the third model requires spin and parity distributions for all excited states that cannot be supplied by either one of the first two models. A… more

Date: August 15, 2001

Creator: Fu, C.Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

TNG-GENOA User's Manual

The aim of this work is to describe the basic aspects of the codes TNG and GENOA. These codes have been developed and used at ORNL in the last decades for the analysis and evaluation of neutron induced nuclear data. In the energy region of the unresolved resonances range and high energies range. These evaluations have been performed in support of various projects and were included in the ENDF/B library. The implementation of these codes into the code SAMMY has been performed as part of a progra… more

Date: October 1, 2000

Creator: Guimaraes, F.B. & Fu, C.Y.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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CALOR as a Single Code Including a Modular Version of HETC

The major components of CALOR are HETC, MORSE, EGS4, EGS4PREP, and SPECT, working sequentially on calorimeter detector for high energy physics, experimental analysis, or shielding studies. An effort to combine the components into a single code is described. The new code is modular in nature. For example, one may run only HETC and MORSE. In addition, HETC itself has become modular and may be run in three energy options--up to 2.5 GeV, 15 GeV, and 20 TeV. The size of the low-energy option of HETC… more

Date: September 14, 1998

Creator: Fu, C.Y. & Gabriel, T.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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HETC96/MORSE calculations of activations in KEK beam stop and room by 500-MeV protons and comparisons with experiments

The 1996 version of HETC has a pre-equilibrium reaction model to bridge the gap between the existing intranuclear-cascade and evaporation models. This code was used to calculate proton-induced activations, to calculate neutron fluxes for neutron energies above 19.6 MeV, and to write the neutron source for lower energies to be transported further by MORSE. For MORSE, the HILO cross section library was used for neutron transport for all detectors. Additionally for the {sup 197}Au(n, {gamma}) dete… more

Date: May 1, 1997

Creator: Fu, C.Y. & Gabriel, T.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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PICA95: An intranuclear-cascade code for 25-MeV to 3.5-GeV photon-induced nuclear reactions

PICA95, an intranuclear-cascade code for calculating photon-induced nuclear reactions for incident photon energies up to 3.5 GeV, is an extension of the original PICA code package that works for incident photon energies up to 400 MeV. The original code includes the quasi-deuteron breakup and single-pion production channels. The extension to an incident photon energy of 3.5 GeV requires the addition of multiple-pion production channels capable of emitting up to five pions. Relativistic phase-spa… more

Date: May 1, 1997

Creator: Fu, C.Y.; Gabriel, T.A. & Lillie, R.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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A neural manufacturing a novel concept for processing modeling, monitoring and control

Semiconductor fabrication lines have become extremely costly, and achieving a good return from such a high capital investment requires efficient utilization of these expensive facilities. It is highly desirable to shorten processing development time, increase fabrication yield, enhance flexibility, improve quality, and minimize downtime. We propose that these ends can be achieved by applying recent advances in the areas of artificial neural networks, fuzzy logic, machine learning, and genetic a… more

Date: October 1, 1995

Creator: Law, B.; Fu, C.Y. & Petrich, L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Effects of shape differences in the level densities of three formalisms of calculated cross sections

Effects of shape differences in the level densities of three formalisms on calculated cross sections and particle emission spectra are described. Reactions for incident neutrons up to 20 MeV on {sup 58}Ni are chosen for illustrations. Level-density parameters for one of the formalisms are determined from the available neutron resonance data for one residual nuclide in the binary channels and from fitting the measured (n, n{prime}), (n, p), and (n, {alpha}) cross sections for the other two resid… more

Date: September 1, 1995

Creator: Fu, C.Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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TNG calculations and evaluations of photon production data for some ENDF/B-VI materials

Among the new evaluations in the ENDF/B-VI general purpose files, 25 were based on calculations using TNG, a consistent Hauser-Feshbach pre-equilibrium nuclear model code. The photon production cross sections and spectra were calculated simultaneously with the particle emission cross sections and spectra, assuring energy balance for each reaction. The theories used in TNG for these calculations are summarized. Several examples of photon production data, taken from the ENDF/B-VI files, are compa… more

Date: December 31, 1994

Creator: Fu, C.Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Radiation Levels in the Ssc Experimental Facilities

Because of the increase in beam energy and intensity at the Superconducting Super Collider Laboratory (SSCL) accelerator, the biological shielding necessary for the experimental halls as well as the shielding for various detector components will require a much more critical review than that carried out for previous high energy physics facilities such as the Fermi National Accelerator Laboratory (FNAL) or the Stanford Linear Accelerator Center (SLAC). This paper summarizes studies of the neutron… more

Date: October 1, 1993

Creator: Alsmiller, F. S.; Alsmiller, R. G., Jr.; Fu, C. Y.; Gabriel, T. A.; Lillie, R. A. & Slater, C. O.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Evaluation of the silicon isotopes for ENDF/B-VI

Isotopic evaluations for {sup 28,29,30}Si performed for ENDF/B-VI are briefly reviewed. The evaluations are based on analysis of experimental data and results of model calculations. Evaluated data are given for neutron induced reaction cross sections, angular and energy distributions, and gamma-ray production cross sections. All necessary data are given to allow KERMA (Kinetic Energy Released in MAterials) and displacement cross sections to be calculated directly from information available in t… more

Date: January 1, 1991

Creator: Hetrick, D. M.; Larson, D. C.; Larson, N. M.; Fu, C. Y. & Epperson, S. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Experimental and calculated excitation functions for discrete-line gamma-ray production due to 1-40 MeV neutron interactions with sup 56 Fe

Measuring cross sections for gamma-ray production from tertiary reactions is one of the ways to gain experimental information about these reactions. To this end, inelastic and other nonelastic neutron interactions with {sup 56}Fe have been studied for incident neutron energies between 0.8 and 41 MeV. An iron sample isotopically enriched in the mass 56 isotope was used. Gamma rays representing 70 transitions among levels in residual nuclei were identified, and production cross sections were dedu… more

Date: January 1, 1991

Creator: Dickens, J.K.; Fu, C.Y.; Hetrick, D.M.; Larson, D.C. & Todd, J.H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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International evaluation cooperation Task 1. 1: Intercomparison of evaluated files for sup 52 Cr, sup 56 Fe, and sup 58 Ni

The cross sections and energy and angular distributions in the JENDL-3, JEF-2/EFF-2, and ENDF/B-VI evaluations for {sup 52}Cr, {sup 56}Fe, and {sup 58}Ni are compared graphically. The purpose is to understand the reasons for observed discrepancies among the evaluations, and to suggest recommendations for improvements. The accomplishments to date are presented.

Date: January 1, 1991

Creator: Fu, C.Y.; Larson, D.C.; Hetrick, D.M. (Oak Ridge National Lab., TN (USA)); Vonach, H. (Vienna Univ. (Austria)); Kopecky, J. (Netherlands Energy Research Foundation, Petten (Netherlands)); Iijima, S. (Toshiba Corp., Kawasaki (Japan). Nuclear Engineering Lab.) et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

The Liquid Argon Calorimeter Subsystem

During the past several months, Tennessee, Mississippi, and the Oak Ridge National Laboratory have been coordinating efforts to benchmark the CALOR89 code system against the DO and HELIOS prototype calorimeter data, and to use the CALOR89 system to generate currently needed data for radiation damage studies, signal collection time, and compensation characteristics of various calorimeter designs. This report describes these results and gives our plans and projected budgets for the following year… more

Date: January 1, 1991

Creator: Alsmiller, R. G., Jr.; Fu, C. Y.; Gabriel, T. A.; Handler, T.; Cremaldi, L. & Reidy, J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Potential improvements to ENDF/B-VI for fusion data

While ENDF/B-6 is significant improvement over previous versions for fusion reactor design calculations, several areas have not received attention and may need improvement. In addition, broadening of the contents of the evaluations to contain information not easily derived at present should be considered. 11 refs.

Date: January 1, 1991

Creator: Larson, D.C. & Fu, C.Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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The Scintillating Plate Calorimeter Subsystem

During the past year, Tennessee, Mississippi, and Oak Ridge National Laboratory have been coordinating efforts to benchmark the CALOR89 code system against the ZEUS prototype calorimeter data, and to use the CALOR89 system to generate currently needed data for radiation damage studies, signal collection time, and compensation characteristics of various calorimeter designs. This report describes these results and gives our plans and projected budgets for the following year. 7 refs., 7 figs., 1 t… more

Date: January 1, 1991

Creator: Handler, T.; Reidy, J.; Cremaldi, L.; Alsmiller, R. G., Jr.; Fu, C. Y. & Gabriel, T. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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(Evaluations of neutron reactions with sup 52 Cr, sup 56 Fe, sup 58 Ni)

The traveler organized and chaired the meeting of the NEANDC/NEACRP Nuclear Data Evaluation Cooperation Subgroup-I: Intercomparison of USA, European, and Japanese Evaluations for {sup 52}Cr, {sup 56}Fe, and {sup 58}Ni, held on December 3, 1990, at the NEA Data Bank in Saclay, France. The traveler held discussions with Subgroup-II members to keep track of the activities of this group in which the traveler is a member. Highlights and/or recommendations of these meetings, as well as observations o… more

Date: December 21, 1990

Creator: Fu, C.Y.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Calculated cross sections for neutron induced reactions on sup 19 F and uncertainties of parameters

Nuclear model codes were used to calculate cross sections for neutron-induced reactions on {sup 19}F for incident energies from 2 to 20 MeV. The model parameters in the codes were adjusted to best reproduce experimental data and are given in this report. The calculated results are compared to measured data and the evaluated values of ENDF/B-V. The covariance matrix for several of the most sensitive model parameters is given based on the scatter of measured data around the theoretical curves and… more

Date: September 1, 1990

Creator: Zhao, Z.X. (Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy); Fu, C.Y. & Larson, D.C. (Oak Ridge National Lab., TN (USA))

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Accurate calculations of neutron kerma (Kinetic Energy Released in MAterials) and damage from ENDF/B-VI evaluations for silicon, chromium, iron and nickel, and comparison with ENDF/B-V results

Accurate calculations of kerma (Kinetic Energy Released in MAterials) factors and displacement cross sections are fundamental to studies of neutron heating and neutron radiation damage. Damage and heating studies are important elements in both fission and fusion reactor design. For fusion reactor studies, heating in the blanket helps determine the efficiency, and heating studies in the superconducting magnet regions determine properties of the blanket and shield, thereby affecting the economics… more

Date: January 1, 1990

Creator: Larson, D. C.; Hetrick, D. M.; Fu, C. Y.; Epperson, S. J. & MacFarlane, R. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

CALOR89: Calorimetry Analysis and Benchmarking

The CALOR89 code system has been utilized for extensive calorimeter benchmarking and design calculations. Even though this code system has previously demonstrated its power in the design of calorimeters, major revisions in the form of better collision models and cross-section data bases have expanded its capabilities. The benchmarking has been done with respect to the ZEUS and DO calorimeters. For the most part, good agreement with experimental data has been obtained. The design calculations pr… more

Date: January 1, 1990

Creator: Gabriel, T. A.; Alsmiller, R. G., Jr.; Bishop, B. L.; Fu, C. Y. (Oak Ridge National Lab., TN (USA)); Handler, T. (Tennessee Univ., Knoxville, TN (USA)); Panakkal, J. K. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Improvements in ENDF/B-VI iron and possible impacts on pressure vessel surveillance dosimetry

The ENDF/B-VI cross-section evaluations for the four iron isotopes are summarized, emphasizing the major improvements over ENDF/B-V. The evaluations were mostly based on a preliminary file generated in 1986 for natural iron that has been used for re-calculating several neutron-transport experiments, of all which showed improved agreement. These re-analyses, including those for pressure-vessel surveillance dosimetry, are also discussed. 20 refs., 3 figs.

Date: January 1, 1990

Creator: Fu, C. Y.; Hetrick, D. M.; Perey, C. M.; Perey, F. G.; Larson, N. M. & Larson, D. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Generation of broad-group neutron/photon cross-section libraries for shielding applications

The generation and use of multigroup cross-section libraries with broad energy group structures is primarily for the economy of computer resources. Also, the establishment of reference broad-group libraries is desirable in order to avoid duplication of effort, both in terms of the data generation and verification, and to assure a common data base for all participants in a specific project. Uncertainties are inevitably introduced into the broad-group cross sections due to approximations in the g… more

Date: January 1, 1989

Creator: Ingersoll, D. T.; Roussin, R. W.; Fu, C. Y. & White, J. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Pairing interaction effects in exciton level densities

Recent progress in pairing corrections for exciton state-density formulas used in pre-compound nuclear reaction theories is reviewed. These correction factors are, strictly speaking, dependent on the nuclear excitation energy U and the exciton number n. A simple formula for (U,n)-dependent pairing corrections has been derived, based on the BCS pairing equations for constant single-particle spacing, for the exciton state-density formula for one kind of Fermion. It has been shown that the constan… more

Date: January 1, 1989

Creator: Fu, C.Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department