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Volumn 2, Issue , 2007, Pages 1115-1119

Passive neutron detection at borders

Author keywords

[No Author keywords available]

Indexed keywords

NEUTRON DETECTORS; NEUTRONS; RADIOACTIVE MATERIALS;

EID: 48349129149     PISSN: 10957863     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1109/NSSMIC.2007.4437203     Document Type: Conference Paper
Times cited : (10)

References (10)
  • 4
    • 37549006884 scopus 로고    scopus 로고
    • in Public Protection from Nuclear, Chemical, and Biological Terrorism
    • eds. A Brodsky and RH Johnson, Jr, Medical Physics Publishing, Madison, Wisconsin, pp, July
    • R.T. Kouzes, Chapter 3 in Public Protection from Nuclear, Chemical, and Biological Terrorism. The 2004 Health Physics Society Summer School, eds. A Brodsky and RH Johnson, Jr., Medical Physics Publishing, Madison, Wisconsin, pp. 31-46 (July 2004).
    • (2004) The 2004 Health Physics Society Summer School , pp. 31-46
    • Kouzes, R.T.1
  • 5
    • 37549021974 scopus 로고    scopus 로고
    • Detecting Illicit Nuclear Materials
    • September-October
    • R.T. Kouzes, "Detecting Illicit Nuclear Materials", American Scientist 93, pp. 422-427, (September-October 2005).
    • (2005) American Scientist , vol.93 , pp. 422-427
    • Kouzes, R.T.1
  • 6
    • 33646757537 scopus 로고    scopus 로고
    • Baseline Suppression of Portal Monitor Vehicle Gamma Count Profiles: A Characterization Study
    • C.A. LoPresti, D.R. Weier, R.T. Kouzes, J.E. Schweppe, Baseline Suppression of Portal Monitor Vehicle Gamma Count Profiles: A Characterization Study, Nuclear Instruments & Methods A 562, pp. 281-297 (2006).
    • (2006) Nuclear Instruments & Methods A , vol.562 , pp. 281-297
    • LoPresti, C.A.1    Weier, D.R.2    Kouzes, R.T.3    Schweppe, J.E.4
  • 7
    • 48349128866 scopus 로고    scopus 로고
    • MCNP X-5 Monte Carlo Team, MCNP - A General Purpose Monte Carlo N-Particle Transport Code, Version 5, LA-UR-03-1987, Los Alamos National Laboratory, April 2003. The MCNP code can be obtained from the Radiation Safety Information Computational Center (RSICC), P. O. Box 2008, Oak Ridge, TN, 37831-6362.
    • MCNP X-5 Monte Carlo Team, MCNP - A General Purpose Monte Carlo N-Particle Transport Code, Version 5, LA-UR-03-1987, Los Alamos National Laboratory, April 2003. The MCNP code can be obtained from the Radiation Safety Information Computational Center (RSICC), P. O. Box 2008, Oak Ridge, TN, 37831-6362.
  • 9
    • 0344956301 scopus 로고
    • Principles of Total Neutron Counting
    • Nuclear Regulatory Commission NRC-FIN-A7241, pp
    • J.E. Stewart, Principles of Total Neutron Counting, in Passive Nondestructive Assay of Nuclear Materials (PANDA), Nuclear Regulatory Commission NRC-FIN-A7241, pp. 407-434 (1991).
    • (1991) Passive Nondestructive Assay of Nuclear Materials (PANDA) , pp. 407-434
    • Stewart, J.E.1
  • 10
    • 48349141946 scopus 로고    scopus 로고
    • W.B. Wilson, R.T. Perry, W.S. Charlton, T.A. Parish, G.P. Estes, T.H. Brown, E.D. Author, M. Bozoian, T.R. England, D.G. Madland, J.E. Stewart, SOURCES-4A: A Code for Calculating (alpha, n), Spontaneous Fission, and Delayed Neutron Sources and Spectra, Los Alamos National Laboratory Report LA-13639-MS (September 1999).
    • W.B. Wilson, R.T. Perry, W.S. Charlton, T.A. Parish, G.P. Estes, T.H. Brown, E.D. Author, M. Bozoian, T.R. England, D.G. Madland, J.E. Stewart, SOURCES-4A: A Code for Calculating (alpha, n), Spontaneous Fission, and Delayed Neutron Sources and Spectra, Los Alamos National Laboratory Report LA-13639-MS (September 1999).


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.