Skip to main content

The U.S. U-235 Fission Spectrum Standard Neutron Field Revisited

  • Chapter
Reactor Dosimetry

Abstract

As use is made of a standard neutron field, formerly unidentified needs and ways to improve its performance became apparent. This paper presents improvements in calibration techniques, results of Monte Carlo calculations which better define scattering corrections, and new handling procedures which improve reproducibi1ity and decrease radiation exposure to personnel. Also, an application of the NBS 235U fission spectrum to test consistency among laboratories who analyze surveillance dosimetry for reactor pressure vessel exposures is summarized.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 39.99
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 54.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. Compendium of Benchmark and Test Region Neutron Fields for Pressure Vessel Irradiation Surveillance; Standard Neutron Spectra. NRC NUREG/CR-0551, Progress Report--July-Sept. 1978 (Dec. 1978).

    Google Scholar 

  2. “Neutron Fluence and Cross. Section Measurements for Fast Neutron Dosimetry,” G. P. Lamaze, D. M. Gilliam, E. D. McGarry, NBS, Gaithersburg, Maryland; A. Fabry, SCK/CEN Laboratory, Mol, Belgium; Proc. of Int’l. Conf. Nucl. Meth. and Environ, and Energy Res., San Juan, PR (April 1984) (Proc. to be published by Department of Energy).

    Google Scholar 

  3. “Cross Section Measurements in the 235U Fission Spectrum Neutron Field,” D. M. Gilliam, J. A. Grundl, G. P. Lamaze, C. M. Eisenhauer, NBS, Gaithersburg, Maryland; A. Fabry, SCK/CEN Laboratory, Mol, Belgium (Sept. 1984). (This ASTM/EURATOM Symposium.)

    Google Scholar 

  4. “The Mol Cavity Fission Spectrum Standard Neutron Field and Its Applications,” A. Fabry, G. Minsart, F. Cops, and S. DeLeeuw; Proc. Fourth ASTM/EURATOM Symposium on Reactor Dosimetry, Washington, DC (March 1982).

    Google Scholar 

  5. E. D. McGarry, “Requirements for Referencing Reactor Pressure Vessel Surveillance Dosimetry to Benchmark Neutron Field” in Nuclear Data for Radiation Damage Assessment and Related Safety Aspects, Proc. of the Advisory Group Meeting, Vienna, Austria, Oct. 12–16, 1981; IAEA-TECD0C-263 (1982).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Editor information

Editors and Affiliations

Rights and permissions

Reprints and permissions

Copyright information

© 1985 Springer Science+Business Media Dordrecht

About this chapter

Cite this chapter

McGarry, E.D., Eisenhauer, C.M., Gilliam, D.M., Grundl, J.A., Lamaze, G.P. (1985). The U.S. U-235 Fission Spectrum Standard Neutron Field Revisited. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-010-9726-0_27

Download citation

  • DOI: https://doi.org/10.1007/978-94-010-9726-0_27

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-94-010-9728-4

  • Online ISBN: 978-94-010-9726-0

  • eBook Packages: Springer Book Archive

Publish with us

Policies and ethics