Inversion point of the isothermal reactivity coefficient of the IPEN/MB-01 reactor - 1: Experimental procedure

Nuclear Science and Engineering

Volumn 133, Issue 3, 1999, Pages 314-326

  Dos Santos, A ^a   Pasqualeto, H ^a   Fanaro, L C C B ^a   Fuga, R ^a   Jerez, R ^a  

^a INSTITUTO DE PESQUISAS ENERGÉTICAS E NUCLEARES   (Brazil)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING; HEATING; REACTIVITY (NUCLEAR); URANIUM;

ISOTHERMAL REACTIVITY COEFFICIENT;

LIGHT WATER REACTORS;

EID: 0033221890     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE99-A2091     Document Type: Article

References (41)

1. "Cross Section Evaluation Working Group Benchmark Specification," ENDF-202 (BNL-19302), Brookhaven National Laboratory.
2. S. R. BIERMAN, E. D. CLAYTON, and L. E. HANSEN, "Critical Experiments with Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8, 15, and 30 wt% Plutonium," Nucl. Sci. Eng., 50, 115 (1973).
3. 2 Rods in Water," Nucl. Sci. Eng., 71, 154 (1979).
4. J. HARDY, Jr., D. KLEIN, and J. J. VOLPE, "A Study of Physics Parameters in Several Water-Moderated Lattices of Slightly Enriched and Natural Uranium," WAPD-TM-931, Bettis Atomic Power Laboratory (Mar. 1970).
5. S. STIRAMAN, "MCNP: Light Water Reactor Critical Benchmarks," NEDO-32028, General Eletric Nuclear Energy (1992).
6. "Topics Light Water Reactor Physics: Final Report on the NORA Project," Technical Report Series No. 133, IAEA-R-104, International Atomic Energy Agency (1970).
7. 2 Lattices," JAERI-1254, Japan Atomic Energy Research Institute (1977).
8. 2O/Fuel Pin Lattices at Temperatures Up to 245°C," STUDSVIK/NS-90/133, Studsvik Energiteknik AB (1990).
9. 2O," BAW-1233, Babcock and Wilcox Company (1962).
10. 2," AEEW-R-455, UKAEA Atomic Energy Establishment (1966).
11. S. SITARAMAN and F. RAHNEMA, "Criticality Analysis of Heterogeneous Light Water Reactor Configurations," Nucl. Sci. Eng., 113, 239 (1993).
12. C. GOLINELLI et al., "Temperature Coefficient and Doppler Effect Measurements," presented at Topl. Mtg. Advances in Reactor Physics and Shield, Sun Valley, Idaho (1980).
13. A. SANTOS, H. YORIYÁZ, R. FUGA, and R. JEREZ, "Reactivity Coefficients of IPEN/MB-01 Reactor," Proc. Int. Conf. Physics of Reactors, PHYSOR-96, Mito, Ibaraki, Japan, September 16-20, 1996 (1996).
14. G. D. SPRIGGS, "Two Rossi-α Techniques for Measuring the Effective Delayed Neutron Fraction," Nucl. Sci. Eng., 113, 161 (1993).
15. G. D. SPRIGGS, "In-Pile Measurement of the Decay Constants and Relative Abundance of Delayed Neutrons," Nucl. Sci. Eng., 114, 342 (1993).
16. J. HARDY, "ENDF/B Data Testing Results for Thermal Reactor Benchmark," Proc. Thermal Reactors Benchmark Calculations: Techniques, Results, and Applications, EPRI-NP-2885, Bettis Atomic Power Laboratory (Feb. 1983).
17. F. RAHNEMA and S. MEKINLEY, "On the Validation of ENDF/B-VI Nuclear Data for Light Water Reactor Criticality Analysis," Ann. Nucl. Energy, 24, 14, 1151 (1997).
18. J. HARDY and A. C. KAHLER, "Analysis of Benchmark Critical Experiments with ENDF/B-VI Data Sets," Proc. Int. Topl. Mtg. Advances in Mathematic Computations and Reactor Physics, Pittsburgh, Pennsylvania, April 28-May 2, 1991, p. 19.1 1-1, American Nuclear Society (1991).
19. J. L. IVERSON and R. D. MOSTELLER, "Results of MCNP Calculations for Criticality Safety Benchmarks with ENDF/B-V and ENDF/B-VI Libraries," Trans. Am. Nucl. Soc., 72, 199 (1995).
20. N. D. KEEN, S. C. FRANKLE, and R. E. MacFARLANE, "Criticality Benchmark Results for the ENDF60 Library with MCNP," Trans. Am. Nucl. Soc., 73, 216 (1995).
21. J. KIM and C. GIL, "The MCNP Analysis of BWR-Simulated Critical Experiments with ENDF/B-V1.2 and JEF-2.2," Trans. Am. Nucl. Soc., 73, 446 (1995).
22. M. L. WILLIAMS, R. Q. WRIGHT, and M. ASGARI, "ENDF/B-VI Performance for Thermal Reactor Analysis," Trans. Am. Nucl. Soc., 73, 420 (1995).
23. "ENDF/B-VI Summary Documentation," BNL-NCS-17541 (ENDF-201), 4th ed. (ENDF/B-VI), P. F. ROSE, Ed., National Nuclear Data Center, Brookhaven National Laboratory (1991; Release-21993; Release-3 1995).
24. T. NAKAGAWA et al., "Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL 3.2," J. Nucl. Sci. Technol., 32, 1259 (1995).
25. H. D. LEMMEL, IAEA-NDS-120, Rev.2., International Atomic Energy Agency (1993).
26. 240Pu," Nucl. Sci. Eng., 96, 318 (1987).
27. n = 0.01 eV to 60 eV)," Nucl. Sci. Eng., 88, 37 (1984).
28. R. C. SCHRACK, "Measurement of the U-235 (n,f) Reaction from Thermal to 1 keV," Proc. Int. Conf. Nuclear Data for Science and Technology, Mito, Japan, May 30-June 3, 1988, Japan Atomic Energy Research Institute (1988).
29. 239Pu," Proc. Int. Conf. Nuclear Data for Science and Technology, Mito, Japan, May 30-June 3, 1988, Japan Atomic Energy Research Institute (1988).
30. 239Pu," Proc. Int. Conf. Nuclear Data for Science and Technology, Mito, Japan, May 30-June 3, 1988, Japan Atomic Energy Research Institute (1988).
31. 235U Neutron-Induced Cross Sections Up to 500 eV," Nucl. Sci. Eng., 109, 1 (1991).
32. C. MOUNIER, "Contribution a Létude du Coefficient de Temperature des Reactures a Eau Legere," CEA-N-2761, Commissariat à l'Energy Atomique (1994).
33. A. SANTAMARINA, "Nuclear Data for the Calculation of Thermal Reactor Reactivity Coefficients," IAEA-TECDOC 491, International Atomic Energy Agency (1989).
34. J. BOUCHARD, C. GOLINELLI, and H. TELLIER, "Besoins en Donneés Nucléaires pour les Réacteurs a Neutron Thermique," Proc. Int. Conf. Nuclear Data for Science and Technology, 1983, p. 21.
35. A. SANTAMARINA, C. GOLINELLI, and L. ERADI, "Temperature Effect Analysis in Light Water Reactor Lattices," presented at ANS Topl. Mtg. Reactor Physics, Chicago, Illinois, 1984.
36. A. SANTAMARINA and H. TELLIER, "The French CEA 86 Multigroup Cross Section Library and Its Integral Qualification," Proc. Int. Conf. Nuclear Data for Science and Technology, Mito, Japan, May 30-June 3, 1988, p. 47, Japan Atomic Energy Research Institute (1988).
37. H. WIGMAN et al., "Measurements of η of U-235 for Sub-Thermal Neutron Energies," Proc. Int. Conf. Physics of Reactors: Operation, Design, and Computation, Physor-90, Marseille, France, April 23-26, 1990.
38. 235U in the Energy Region Below 1 eV," Proc. Int. Conf. Nuclear Data for Science and Technology, Mito, Japan, May 30-June 3, 1988, p. 75, Japan Atomic Energy Research Institute (1988).
39. 239," J. Nucl. Energy, 1, 177 (1956).
40. A. SANTOS, "Some ENDF/B-VI Benchmark Results," Trans. Am. Nucl. Soc., 76, 332 (1997).
41. D. L. SMITH, "Probability Statistics and Data Uncertainties in Nuclear Science and Technology," American Nuclear Society, LaGrange Park, Illinois (1991).