Argonne National Laboratory
RERTR
Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

RERTR Publications:
Analysis Methods for Thermal Research and Test Reactors

ANL/RERTR/TM-29

COMPUTING CONTROL ROD WORTHS
IN THERMAL RESEARCH REACTORS

REFERENCES

1. C. W. Maynard, "Blackness Theory and Coefficients for Slab Geometry," Nucl. Sci.
Eng. 6, 174 (1959). Also, C. W. Maynard, "Blackness Theory for Slabs," in Naval
Reactors Physics Handbook, Vol. I, A. Radkowsky, Editor, pp. 409-448, U.S. AEC
(1964).

2. S. P. Congdon and M. R. Mendelson, "PN Blackness Theory in Plane Geometry," Nucl.Sci. Eng. 33, 151-161 (1968).

3. M. M. Bretscher, "Blackness Coefficients, Effective Diffusion Parameters, and Control
Rod Worths for Thermal Reactors," ANL/RERTR/TM-5, September 1984.

4. K. L. Derstine, "DIF3D: A Code to Solve One, Two, and Three Dimensional Finite
Difference Theory Problems," ANL-82-64, April 1984.

5. W. Kerr, J. S. King, J. C. Lee, W. R. Martin, and D. K. Wehe, "The Ford Nuclear
Reactor Demonstration Project for the Evaluation and Analysis of Low Enrichment
Fuel - Final Report," ANL/RERTR/TM-17, July 1991.

6. L. J. Templin, Ed., "Reactor Physics Constants," 2nd Edition, pp. 361-363, ANL-
5800, July 1963.

7. C. I. Costescu, J. R. Deen, and W. L. Woodruff, "WIMS-D4M USER MANUAL,"
ANL/RERTR/TM-23, July 1995.

8. R. E. Alcouffe, F. W. Brinkley, D. R. Marr, and D. D. O'Dell, "User's Guide for
TWODANT: A Code Package for Two-Dimensional, Diffusion-Accelerated, Neutral-
Particle, Transport," LA-10049-M, February 1, 1990.

9. R. Bloomquist, "VIM - A Continuous Energy Neutronics and Photon Transport
Code." pp. 222-224, ANS Proceedings of the Topical Meeting on Advances in
Reactor Computations, Salt Lake City, Utah, March 28-31, 1983.

10. M. M. Bretscher and R. J. Snelgrove, "The Whole-Core LEU U3Si2-Al Fuel
Demonstration in the 30-MW Oak Ridge Research Reactor," ANL/RERTR/TM-14,
July 1991.

11. J. E. Matos and K. E. Freese, "Safety Analyses for HEU and LEU Equilibrium Cores
and HEU-LEU Transition Core for the IAEA Generic 10 MW Reactor," IAEA-
TECDOC-643, Vol. 2, pp. 29-51, Vienna, April 1992.

12. H. Icikawa, H. Ikawa, H. Ando, M. Takayagi, H. Tsuruta, and Y. Miyasaks,
"Neutronic and Thermo-Hydraulic Design of JRR-3(M) Reactor," Proceedings of the
International Meeting on Reduced Enrichment for Research and Test Reactors,"
October 24-27, 1983, Tokai, Japan (May 1984).

13. J. A. Rathkopf, C. R. Drum, W. R. Martin, and J. C. Lee, "Analysis of the Ford
Nuclear Reactor LEU Core," Proceedings of the International Meeting on Research
and Test Reactor Core Conversions from HEU to LEU Fuel, Argonne, November 8-
10, 1982, ANL/RERTR/TM-4 (CONF-821155), September 1983.

14. J. F. Briesmeister, Ed., "MCNP-A General Monte Carlo N-Particle Transport Code,"
Version 4A Manual, LA-12625-M, November 1993.

15. M. Bretscher, "Blackness Coefficients, Effective Diffusion Parameters, and Control
Rod Worths for Thermal Reactors - Applications," Proceedings of the 1984
International Meeting on Reduced Enrichment for Research and Test Reactors,"
Argonne, October 15-18, 1984, ANL/RERTR/TM-6 (CONF-8410173), July 1985.

16. J. C. Lee, University of Michigan, provided an unpublished copy of the October 1995
FNR shim-safety rod worth measurements (December 1996).

17. E. M. Gelbard, Argonne National Laboratory, personal communication, 1983.

2016 RERTR Meeting

The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium. Stay tuned for further details.

2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.


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9700 South Cass Ave., Argonne, IL 60439-4814
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Last modified on July 29, 2008 11:33 +0200