Filters
Results 1 - 10 of 55
Results 1 - 10 of 55.
Search took: 0.019 seconds
Sort by: date | relevance |
AbstractAbstract
No abstract available
Primary Subject
Record Type
Journal Article
Journal
Journal of Computational Physics; v. 11(1); p. 109-126
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
18. annual American Nuclear Society conference; Las Vegas, Nev; 18 Jun 1972; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 15(1); p. 265-266
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Shultis, J.K.; Buranapan, W.; Eckhoff, N.D.
Kansas State Univ., Manhattan (USA). Dept. of Nuclear Engineering1981
Kansas State Univ., Manhattan (USA). Dept. of Nuclear Engineering1981
AbstractAbstract
[en] Of considerable importance in the safety analysis of nuclear power plants are methods to estimate the probability of failure-on-demand, p, of a plant component that normally is inactive and that may fail when activated or stressed. Properties of five methods for estimating from failure-on-demand data the parameters of the beta prior distribution in a compound beta-binomial probability model are examined. Simulated failure data generated from a known beta-binomial marginal distribution are used to estimate values of the beta parameters by (1) matching moments of the prior distribution to those of the data, (2) the maximum likelihood method based on the prior distribution, (3) a weighted marginal matching moments method, (4) an unweighted marginal matching moments method, and (5) the maximum likelihood method based on the marginal distribution. For small sample sizes (N = or < 10) with data typical of low failure probability components, it was found that the simple prior matching moments method is often superior (e.g. smallest bias and mean squared error) while for larger sample sizes the marginal maximum likelihood estimators appear to be best
Primary Subject
Source
Dec 1981; 167 p; Available from NTIS., PC A08/MF A01
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This book presents discussions of the transport description of radiation penetration, material and structural conditions in shield design, appendices and index. This book explains well the shielding against ionizing radiation, principally neutrons and photons
Primary Subject
Source
1984; 488 p; Prentice Hall Inc; Old Tappan, NJ (USA); ISBN 0-13-709907-X; 

Record Type
Book
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Neutron depth profiling (NDP) is a nondestructive technique for determining the concentration of special isotopes within several microns of a sample's surface. Previous NDP analyses, however, have been restricted to samples with plane surfaces. Here samples with curved surfaces are considered. In particular, a method for estimating the energy spectrum of ions emitted from curved surfaces is presented. Also, a robust method for inverting the NDP ion energy spectra is presented that yields accurate concentration profiles for both under- and overdetermined NDP spectra
Primary Subject
Source
S0168900204005273; Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment; ISSN 0168-9002;
; CODEN NIMAER; v. 526(3); p. 359-375

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Nason, R.R.; Shultis, J.K.; Faw, R.E.; Clifford, C.E.
Sandia National Labs., Albuquerque, NM (USA); Kansas State Univ., Manhattan (USA); Radiation Research Associates, Inc., Fort Worth, TX (USA)1982
Sandia National Labs., Albuquerque, NM (USA); Kansas State Univ., Manhattan (USA); Radiation Research Associates, Inc., Fort Worth, TX (USA)1982
AbstractAbstract
[en] A benchmark gamma-ray skyshine experiment is descibed in which 60Co sources were either collimated into an upward 150-deg conical beam or shielded vertically by two different thicknesses of concrete. A NaI(Tl) spectrometer and a high pressure ion chamber were used to measure, respectively, the energy spectrum and the 4π-exposure rate of the air-reflected gamma photons up to 700 m from the source. Analyses of the data and comparison to DOT discrete ordinates calculations are presented
Primary Subject
Source
1982; 13 p; 4. ASTM-EURATOM symposium on reactor dosimetry; Gaithersburg, MD, USA; 22 - 26 Mar 1982; CONF-820321--2; Available from NTIS., PC A02/MF A01 as DE82008190
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Paper No. F78 702-3
Primary Subject
Record Type
Journal Article
Journal
IEEE Transactions on Power Apparatus and Systems; v. PAS-98(2); p. 400-407
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Shultis, J.K.; Eckhoff, N.D.; Johnson, D.E.; Milliken, G.A.
Kansas State Univ., Manhattan (USA). Dept. of Nuclear Engineering1981
Kansas State Univ., Manhattan (USA). Dept. of Nuclear Engineering1981
AbstractAbstract
[en] This user's manual presents a detailed description of two FORTRAN computer codes for analyzing component failure data. The first code SAFE-R is used to analyze data giving the number of observed failures in specified component operation times, while the second code SAFE-D is to be applied to failure data giving the number of failures observed in specified numbers of component demands. The theory behind the many analyses performed by these codes is summarized in a companion report NUREG/CR-2374 'Use of Non-Conjugate Prior Distributions in Compound Failure Models.' A description of the overall program structure and detailed use of the many program commands is presented here. A sample input is given along with the resulting output
Primary Subject
Source
Dec 1981; 51 p; Available from NTIS., PC A04/MF A01
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Transactions of the American Nuclear Society 1975 annual meeting; New Orleans, LA; 8 Jun 1975; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 21 p. 530
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] It is shown that for transport problems involving fine-energy-group structure or light element scattering, the elastic scattering transfer cross sections can be approximated by trapezoid-shaped distributions. In particular, for group structures of equal lethargy widths, the trapezoidal distribution reduces to a triangular shape. These approximate transfer cross sections are readily incorporated into a discrete ordinates code and often produce results superior to those obtained with conventional Legendre expansion techniques
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Nuclear Science and Engineering; v. 62(4); p. 738-743
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |