PIN Diode and Neutron Spectrum Measurements at the Army Pulse Radiation Facility

IEEE Transactions on Nuclear Science

Volumn 41, Issue 6, 1994, Pages 2132-2138

  Oliver, M A ^a  

^a Aberdeen Proving Ground ^*  (United States)

Author keywords

[No Author keywords available]

Indexed keywords

GAMMA RAYS; NEUTRON ACTIVATION ANALYSIS; NEUTRON SCATTERING; NUCLEAR REACTORS; RADIATION DAMAGE; RADIATION SHIELDING; SEMICONDUCTING SILICON; SEMICONDUCTOR DIODES; SPECTROMETERS; SPECTRUM ANALYSIS;

ARMY PULSE RADIATION FACILITY; NEUTRON SPECTRUM MEASUREMENTS; NEUTRON TO GAMMA FIELD RATIO; PIN DIODE;

NEUTRON EMISSION;

EID: 0028726798     PISSN: 00189499     EISSN: 15581578     Source Type: Journal    
DOI: 10.1109/23.340553     Document Type: Article

References (12)

1. ASTM Standard E722-93, “Standard Practice for Characterizing the Neutron Energy Fluence Spectra in Terms of an Equivalent Monoenergentic Neutron Fluence for Radiation-Hardness testing of Electronics” 1993 Annual Book of ASTM Standards, Vol. 12.02, Oct 1993
2. Heimbach, C.R., “The Use of Neutron-Sensitive Diodes as Monitors for 1-MeV Equivalent Neutrons,” Proceedings of the Seventh ASTM-EURATOM Symposium on Reactor Dosimetry, Kluwer Academic Publishers, 1990
3. Morin J. et al., “Measuring 1MeV(Si)Equivalent Neutron Fluences with PIN Silicon Diodes,” Proceeding of Second European Conference on Radiation and its Effects on Components and Systems, Saint-Malo, France 1993
4. Stanka, M.B., “Spectroscopy 400 Meters from a Fission Neutron Source,” from The Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, Vail, CO USA, 1993
5. Kelly J.G. et al., “Use of Silicon Bipolar Transistors as Sensors for Neutron Energy Spectra Determinations,” IEEE Trans. Nucl. Sci., Vol. NS34,No.6, Dec. 1987.
6. ASTM Standard E721-93, “Standard Method for Determining Neutron Energy Spectra With Neutron-Activation Activation Foils for Radiation-Hardness testing of Electronics,” 1993 Annual Book of ASTM Standards, Vol. 12.02, Oct 1993
7. Kelly, J.G. & Vehar, D.W., “Measurements of Neutron Spectra in Varied Environments by the Foil Activation Method with Arbitrary Trials,” SAND 87-1330, Sandia National Laboratories, Albuquerque, NM, Dec. 1987
8. McElroy, W.N., et al., “A Computer-Automated Iterative Method for Neutron Flux Spectra Determination by Foil Activation,” AFWL-TR-67-41,Vol 41, Air Force Weapons Laboratory, Kirtland AFB, New Mexico, Sept. 1967.
9. ASTM Standard E265-93, “Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32,” 1993 Annual Book of ASTM Standards, Vol. 12.02, Oct 1993
10. Grundl, J. Eisenhauer, C., “Compendium of Benchmark Neutron Fields For Reactor Dosimetry,” NBSIR 85–3151, National Institute of Standards and Technology, Gaithersburg, MD Jan. 1986.
11. Kocherov, NP., et al., “International Reactor Dosimetry File(IRDF-90), “ IAEA-NDS-141 Rev 0, International Atomic Energy Agency, August 1990, Brookhaven National Laboratory, Upton, New York
12. Kaul, D.C.& Egbert, S.D., “Radiation Leakage from the Army Pulse Radiation Facility Fast Reactor,” SAIC-89/1423, Science Applications International Corporation, San Diego, CA, May 1989.