Skip to main content
Log in

Measured neutron flux parameters in the USGS TRIGA MARK I reactor

  • Published:
Journal of Radioanalytical and Nuclear Chemistry Aims and scope Submit manuscript

Abstract

Using the Westcott convention, the Westcott flux, \( \varphi_{\text{w}} \); modified spectral index, \( r\sqrt {T_{n} /T_{0} } \); neutron temperature, T n; and gold-based cadmium ratios were determined for various sampling positions in the U.S. Geological Survey (USGS) Training, Research, Isotopes, General Atomic (TRIGA) Mark I reactor. Westcott parameters were determined by a bare multi-monitor method. Thermal-neutron temperature measurements were made using lutetium foils. The differential neutron energy spectrum measurement was obtained using the computer iterative code SAND-II-SNL. Measurement of the neutron spectrum has resulted in a better knowledge of the reactor core and will improve predictive radioisotope production calculations necessary for neutron activation analysis and medical isotope production.

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

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Fig. 1
Fig. 2
Fig. 3

Similar content being viewed by others

References

  1. Safety Analysis Report (2009) United States Geological Survey Research Reactor Docket No. 50-274, License No. R-113

  2. Lamarsh JR (1961) Introduction to nuclear reactor theory. American Nuclear Society, Ithaca

    Google Scholar 

  3. ASTM Standard E261 (2010) doi: 10.1520/E0261-10

  4. Williams JG, Gilliam DM (2011) Metrologia 48:254–262. doi:10.1088/0026-1394/48/6/S03

    Article  Google Scholar 

  5. Westcott CH, Walker WH, Alexander TK (1958) Effective cross-sections and cadmium radios for the neutron spectra of thermal reactors. In: Proceedings of the Second United Nations International Conference of the peaceful uses of atomic energy. Geneva, United Nations, 1–13 Sept 1958, vol. 16, pp 70–76

  6. Denschlag JO (2011) In: Vértes A, Nagy S, Klencsár Z, Lovas RG, Rösch F (eds) Handbook of nuclear chemistry. Springer, Berlin, p 2628

    Google Scholar 

  7. Chart of Nuclides. http://www.nndc.bnl.gov/chart/. Accessed 14 May 2014

  8. Pritychenko B, Mughabghab SF (2012) Nucl Data Sheets 113:3120–3144. doi:10.1016/j.nds.2012.11.007

    Article  CAS  Google Scholar 

  9. Martinho E, Gonçalves IF, Salgado J (2003) Appl Radiat Isot 58:371–375. doi:10.1016/S0969-8043(02)00313-5

    Article  CAS  Google Scholar 

  10. Martinho E, Salgado J, Goncalves IF (2004) J Radioanal Nucl Chem 261:637–643

    Article  CAS  Google Scholar 

  11. Benedict M (1981) Nuclear chemical engineering. McGraw-Hill, New York

    Google Scholar 

  12. Chatani H (2003) Measurement of the Westcott Conventionality Thermal Neutron Flux and Suchlike at Irradiation Facilities of the KUR, JAERI-Conf 2003–06, pp 241–246

  13. Lomakin S, Romanov V, Bochin V (1968) At Energ 24:484–485. doi:10.1007/BF01312410

    Article  Google Scholar 

  14. Hong U, Kang HD, Seo CG, Kang YH (2001) In: Williams JG, Vehar DW, Ruddy FH, Gilliam DM (eds) Reactor dosimetry: radiation metrology and assessment. STP 1398. ASTM International, West Conshohocken

    Google Scholar 

  15. ASTM Standard E721 (2011) doi:10.1520/E0721-11

  16. Kelly JG (1987) Neutron spectrum adjustment with SANDII using arbitrary trial functions. Sandia National Labs, Albuquerque

    Google Scholar 

  17. ASTM Standard E263 (2013) doi:10.1520/E0263-13

  18. Schickler RA, Marcum WR, Reese SR (2013) Nucl Eng Des 262:340–349. doi:10.1016/j.nucengdes.2013.05.004

    Article  CAS  Google Scholar 

  19. Khoo K, Sarmani S, Abugassa I (2007) J Radioanal Nucl Chem 271:419–424. doi:10.1007/s10967-007-0225-y

    Article  CAS  Google Scholar 

  20. Graham J, Landsberger S, Ferreira P, Ihlefeld J, Brennecka G (2012) J Radioanal Nucl Chem 291:503–507. doi:10.1007/s10967-011-1270-0

    Article  CAS  Google Scholar 

  21. Erdtmann G (1976) Neutron activation tables. Verlag Chemie, Weinheim

    Google Scholar 

Download references

Acknowledgments

The authors would like to express their sincere thanks to the reactor staff of the GSTR for their support, funding from the Colorado School of Mines, and the NRC Faculty Development Grant program, Grant Number NRC-HQ-11-G-38-0062.

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to J. C. Braley.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Koehl, M.A., Rundberg, R.S. & Braley, J.C. Measured neutron flux parameters in the USGS TRIGA MARK I reactor. J Radioanal Nucl Chem 306, 31–38 (2015). https://doi.org/10.1007/s10967-015-4058-9

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10967-015-4058-9

Keywords

Navigation