Cadmium Cutoff Energy for MCNP Modeling of Dosimetry Reactions

Author

Peter G. Laky
Nicholas Tsoulfanidis, Missouri University of Science and Technology

Abstract

The MCNP code modeling of reactor cavity dosimetry reactions to validate the computed neutron flux hitting the pressure vessel of a pressurized water reactor (PWR) requires the choice of an appropriate cadmium cutoff energy. Since the neutron spectrum is harder in the cavity than in the core, the same cadmium cutoff energy may not be universally applied. The correct cutoff energy for the cavity of a PWR was computed by using MCNP4a and a representative cavity spectrum. Four cadmium-covered foil reactions were analyzed, and the appropriate energy cutoff was determined to be approximately 0.6 eV for approximately 0.5-mm-thick cadmium covers.

Recommended Citation

P. G. Laky and N. Tsoulfanidis, "Cadmium Cutoff Energy for MCNP Modeling of Dosimetry Reactions," Nuclear Science and Engineering, vol. 118, no. 2, pp. 103 - 107, Taylor and Francis Group; Taylor and Francis; American Nuclear Society, Jan 1994.

The definitive version is available at https://doi.org/10.13182/NSE94-A28539

Department(s)

Nuclear Engineering and Radiation Science

International Standard Serial Number (ISSN)

0029-5639

Document Type

Article - Journal

Document Version

Citation

File Type

text

Language(s)

English

Rights

© 2024 Taylor and Francis Group; Taylor and Francis; American Nuclear Society, All rights reserved.

Publication Date

01 Jan 1994