Devido I dificuldade em se fazer um cálculo exato do efeito de espalhamento Compton n*
44. HARRINGTON, J, Determination of U-235 in irradiated fuel elements by reactivity measurements
AtomWimch. Atomtech., 16(12)«34-5,1971.
45. HART, R. G.; LOUNSBURY, M.; JONES, R. W.; MOTLEY, M. J. F.; A comparison of methods of determining burnup of uranium dioxide fuel test specimens. Nucl. Sci. Engng, 18:6-7, 1964.
46. HIGATSBERGER, M. J . ; HICK, H.; RUMPOLD, K.; WEINSIERL, P.; 8URTHSCHER. A.
Operating experience with the semiconductor gamma-Compton spectrometer to determine the burn-up and burn-up hystory of nuclear fuel. In: INTERNATIONAL ATOMIC ENERGY AGENCY. Nuclear materials management: proceedings of the symposium on... held in Vienna, 30-August - 3 September, 1965. Vienna, 1966. p.817-28. (Proceedings series).
47. HILLER, 5. Gamma spectrometric burnup determination in reactor fuel rods. Kerntechnik, 12:488-90, 1970.
48. INTERNATIONAL ATOMIC ENERGY AGENCY. Reactor burn-up physics: proceedingt.. held in Vienna, 12-16 July 1971. Vienna, 1973. p.39-55.
49. INOUE, K.; TANIGUCHI, K.; KOBAYASHI, T. Mass spectrometric determination of burnup. J.
nucl. Sci. Ttchnol., 4(3) :131-6, 1967.
50. JOHANSSON, E. Some burn-up exDeriments in Sweden. In: INTERNATIONAL ATOMIC ENERGY AGENCY. Reactor burn-up physics: procoodinys. .. held in Vienna. 12-16 July,
1971. Vienna. 1973. p.171 90.
51. JULIEN, J.; MOTTE, F.; BAI, J. Research contract n°5: nondestructive method for evaluating the U23Ò and Pu content of irradiated fuel elements. In: INTERNATIONAL ATOMIC ENERGY AGENCY. IAEA research contracts: second annual report. Vienna, 1962. p.15-7. (Technical reports series, 9).
52. KOCH, L; ARENS, H. J.; BAECKMANN, A. von; CRICCHIO, A.; DE MEESTER, R.;
ROMKOWSKI, M.; STILJ, E. van der; WILHELMI, M. Improvements and experience in the anoiysis of reprocessing samples. In: INTERNATIONAL ATOMIC ENERGY AGENCY.
Salcgurading nuclear materials: proceedinys of a symposium on. . . held in Vienna, 20-24 October 1975. v.2. Vienna, 1976. p.449-60.
53. KOCH, L.; CRICCHIO, A.; GERIN, F. Improved post irradiation analysis for burn-up and heavy isotope content. In: INTERNATIONAL ATOMIC ENERGY AGENCY. Analytical methods in nuclear fuel ,:yle: proceedings... held in Vienna, 29 November - 3 December 1971. Vienna, 1972. p.523-36. (Proceedings series).
64. KRISTIANSEN, P. & ROGERBER, T. Research contract n947: non-destructive analysis of irradiated fuel elements by gamma ray scanning. In: INTERNATIONAL ATOMIC ENERGY AGENCY. IAEA research contracts: second annual report. Vienna, 1962. p.35-7. (Technical reports series, 9).
br-. KRTIL, J.; KRIVANEK, M.; BULOVIC, V.; DJORDJEVIC, M.; MAXIMOVIC, Z. Gamma spectrometric determination of burn-up. In: INTERNATIONAL ATOMIC ENERGY AGENCY.
Analytical methods in the nuclear fuel cycle: proceedings of a symposium on... held in Vienna, 29November- 3December, 1971. Vienna, 1972. p.491-502. (Proceedings series).
C6. LARSON, H. A.; WLAKEH, ".; MEM13»"HTT., 0. EBB II burnup and fluence history I. Parti.
Method and c-des. Idaho Falls., Idaho Argonne fwrinne: L.H., May 1974. (ANL/EBR-O84).
57. LARSON, H. A.; WALKER, P.; SULLiVAN, J. E.; f H h IPS, " . E.; MANEGHETTI, D. EBR-/I burnup and fk'cnce history I. Part. 2. Calculations. Idaho Falls, Idaho, Argonne National Lab., May 1974. (ANL/EBH-085).
58. LADERER, C. M. Table of isotopes. 6.ed. New York, N. Y,, w;^v, 1963.
59. LIN, C. S. & TSAI, J. Non-destructive de. -mination of reactor fuel element burnup by measurement of fission neujvns. J. nu. L Sri. icrhno:., fl:285-7, 1971.
60. LISMAN, F. '_; A^RNATHEY, fl. M.; i.'AECK, W. :..; REIN, J. £. Fiuion yields of over 40 (table and long-lived fission produc: for thermal neutron fissiorsr' 2'JU , 2 3 SU , l 3 9P u , and
2 4 1Pu 9*Á fast reactor fissioned J 3 5ü and a 'Pu. NuJ. Sci. Engng, 4g:161-214, 1970.
61. LISMAN, F. L; MAECK, W. X; REIN, J. E.; POSTER JR., R. F.; ABERNATHEY, R. M.;
DELMORE JR.; J. E.; EMEL, W. A.; KUSSY, M. E.; McARTéE, R. E.; WORKMAN, G. D.
Burnup determination of nuclear fuels. Idaho Falls, Idaho, Idaho Nuclear Corp., Mar. 1968.
(IN-12. 7).
62. LOPEZ-MENCÍIERO, E. The Agency programme for the development of safeguards techniques and Instrumentation. In: INTERNATIONAL ATOMIC ENERGY AGfcNCY. Safeguarding nuclear materials: proceedings..,. in Vienna, 20-24 October 1970, v.2. Vienna, 1976. p.3-15.
63. LUNDE, J. E. Review of burn-up physics work with the Halden Heavy Boilinq-Water Reactor. In:
INTERNATIONAL ATOMIC ENERGY AGENCY. Fuel burn-up predictions in thermal reactors, proceedings... 1967. Vienna, 1968. p.203-11.
64. McGONNAGLE, W. J. Non-destructive methods for determining burn-up in nuclear fuel. In:
I N T E R N A T I O N A L A T O M I C ENERGY A G E N C Y . Nuclear materials management:
proceedings... at Vienna, 30August- 3September 1965. Vienna, 1966. p.851-66.
65. MACIEL, A. C. & CRUZ, P. R. Perfil analítico do urânio. Rio de Janeiro, MME, Departamento Nacional da Produção Mineral, 1973. (Boletim 27).
66. MAECK, W. J. Fission product nuclear data requirements fot the determination of nuclear fuel burnup: a review. In: INTERNATIONAL ATOMIC ENERGY AGENCY. Panel on fission product nuclear data, Bologna, 26-30 Nov. 1973, v.1. Vienna, 1974. (IAEA-169). p. 163 90.
67. MAECK, W. J. & LISMAN, F. L. Bumup determination for fast breeder reactor fuels: program objectives and plans. Idaho Falls, Idaho Nuclear Corp., Feb. 1971. (IN-1456).
68. MAGALHÃES, L. C. A. 0 problema energético brasileiro. [Conferência pronunciada na Escola Superior de Guerra, Rio de Janeiro, 09.09.1975].
60. MARTIN, B. R. Statistics for Physicists. London, Academic, 1971.
70. MASKET, A. V. Solid angle contour integrals, series and tables. Rev. scient Instrum., 28(31:191-7, 1957.
71. MEEK, M. E. & RIDER, B. F. Compilation of fission product yields. Pleasanton, Calif., General Electric Co., Vallecitos Nuclear Center, Jan. 1974. (NEDO-12154-1).
72. MEN LOVE, H. O.; AUGUSTSON, R. H.; SMITH, B. A multi-spectra neutron irradiation technique for the nondestructive assay of fissionable materials. Nucl. Techno!., 1_Q366-79, 1971.
73. MITSUI, H. Burnup analysis of uranium dioxide nondestructive analysis by external conversion method. J. nucl. Sci. Techno!., 3(11)491-5, 1966.
74. MONCASSOLITOSI, A. M.; RAMA, P. G.; BRESESTI, A. M.; BRESESTI, M.; FACCHETTI, S.;
KLERSY, R.; MANNONE, F.; SCHUREMKAMPER, A. Post-irradiation burn-up analysis of Trino-Vercellete Reactor fuel elements. Comparison with theoretical results. In:
INTERNATIONAL ATOMIC ENERGY AGENCY. Reactor burn-up physics: proceedings of a panel on... held in Vienna, 12-16 July 1971. Vienna, 1973. p.it)?-22S. iPar.cl proceedings series).
76. MONIER, J. .Determination i /'aide det tpectrométries alphe et gamma du taux de combustion attaint par let combustibles nucUalnt, Saclay, Fr., CEA, Centre d'Etudts NudéairM, Dec.
1974. (CEA-R-4825).
76. MONSECOUR, M. R. & DEMILDT, A. C. Determination by neutron activation analysis of the burnup indicator neodymlum-148 in irradiated uranium dloxide-plutonium dioxide. Analyt Chern., 4127-31, I960.
77. MUNCH, E. Bum-up determination by Irreversible admixture of rJuence-monitoHng nudldes to nuclear fuel. In: INTERNATIONAL ATOMIC ENERGY AGENCY. Reactor bum-up phytkt:
proceedings... in Vienna, 12-16 July, 1971. Vienna, 1973. p.249-54.
78. NAKAMURA, S. A method for the bumup analysis of power reactor» in equilibrium operation cycle. J. nucl. Sci. Techno!., 2(51:184-8, 1966.
79. NODVIK, R. J. Evaluation of gamma activity distributions in Yankee Corel and Core II spent fuel. Pittsbutg, Pa., Westinghouse Electric Corp. Atomic Power Division, Jun. 1965.
(WCAP6067).
80. NOVIKOV. A. N.; PETRUNIN, D. M.; BELYAEVA, E. D,; I0N0V, V. S,; S H A B A L O V , A. I.;
ROMANOV, B. A. Three-dimensional fuel burn-up calculations in WWER reactors. In:
INTERNATIONAL ATOMIC ENERGY AGENCY. Fuel burn-up predictions in thermal reactors; proceedings of a panel held in Vienna, 10-14 Apr. 1967. Vienna, 1968. p.213-26.
(Panel proceedings series).
81. NUCLEAR power in the United States: the first nine mounths of 1975. Nucl. Energy Dig., (4):3?capa, 1975.
82. ONUSIC Jr., J. Possibilidades teóricas de cálculo do programa de computação HAMMER. SSo Paulo, 1976. (Dissertação de mestrado).
83. OWEN, T. D. Measurement of power and burn-up 'n Irradiated nuclear reactor fuel by a non-destructive method. Br. J. appl. Rhys., 14:466, 1963.
84. PAOLETTI GUALANDI, M.; PERONI, P.; BRESESTI, M.; CUYPERS, M.; D'ADAMO, D.;
LEZZOLI, L. Determination of burnup and plutonlum content In irradiated fuels by gamma-spectrometry measurements of radioactive fission products. In: INTERNATIONAL ATOMIC ENERGY AGENCY. Safeguarding nuclear materials: proceedings of a symposium on... held m Vienna, v.2. Vienna, 1976. 0.613-24.
86. PENNSYLVANIA P & L buys UNC uranium at $56 in 1980 and $62 in '82. Nucleonics Week, 17(44):1, Oct., 1976.
86. PRIESMEYER, H. G. Burnup determination by neutron. Im: INTERNATIONAL ATOMIC ENERGY AGENCY. Panel on fission product nuclear data. Bologna, 26-30 Nov. 1973, v.3.
Vienna, 1974. (IAEA-169). p.57-8.
87. QURESHI, I. H.; LARSEN, E.; TURI, L; OLSEN, J.; HOUGAARD, J. Mass-spectrometric measurement of burn-up in UOj fuel using stable fission product neodymium. In:
INTERNATIONAL ATOMIC ENERGY AGENCY. Analytical methods In the nuclear fuel cycle: proceedings... in Vienna, 29November- 3 Dei-ember, 1971. Vienna, 1972. p.503-11.
(Proceedings series).
88. RAICS, P.; VARNAGY, M.; NAGY, S.; DARÔCZY, S. Application of neutron activation analysis, gamma-spectrometry and nuclear track detectors for reactor fuel assay. In: INTERNATIONAL ATOMIC ENERGY AGENCY. Safeguarding nuclear materials: proceedings on... In Vienna, 20-24 October 1975. v.2. Vienna, 1976. p.641-9.
89. RAIEVSKI, V. & SAUTIEZ, B. Research contract n94: the development of a method of non-destructive analysis to determine the U236 and Pu content of Irradiated fuel elements that are in storage under water and that have been out of the reactor for periods of more than one month. In: INTERNATIONAL ATOMIC ENERGY AGENCY. IAEA research contracts: second annual report. Vienna, 1962. p. 13-4. (Technical reports series, 9).
90. RAMTHUN, H. & OEBERTIN, K. A new possibility for nondestructive burn-up determination. In:
INTERNATIONAL ATOMIC FNER1Y AGFNCY. Analytical methods In the nuclear fuel cycle: proceedings. in Vinnnn, 79 "nmnihrn 't ">*ri>mt)fi 1971 Vienna, 197? p 485-90
91. RASMUSSEN. N. C ; SOVKA, J. A.; MAYMAN, S. A. The nondestructive measurement of burn-up by gamma-ray spectroscopy. In: INTERNATIONAL ATOMIC ENERGY AGENCY.
Nuclear materials management: proceedings... at Vienna, 30 August — 3 September 1965.
Vienna, 1966. p.829 49.
92. RIDER, B. F.; RUIZ, C. P.; PETERSON JR, J. P.; McLAUGHIN, T. V. Burnup: a FORTRAN IV code for computing U and Pu fuel burnup from U, Pu and Nd mass spectrometric measurements. Pleasanton, Calif., General Electric Co., Oct. 1967. (GEAP-5365).
93. RIDER, B. F.; RUIZ, C. P.; PETERSON JR., J. P.; McLAUCHLIN, T. V. Burnup: a FORTRAN IV code for computing U and Pu fuel burnup from U, Pu, and Nd mass spectrometric measurements update for include fast reactor fuels. Sunnyvale, Calif., General Electric Co., Jan.
(GEAP5355A).
9 4 . RIDER, B. F.; RUIZ. C. P.; PETERSON JR, J. P.; SMITH, F. R. Determination of neodymium-148 in irradiated uranium and plutonium at a measure of burnup. Pleasanton, Calif.. General Electric Co., Oct. 1967. (GEAP-6354).
96. RIDER. B. F.; RUSSEL JR, J. L.; HARRIS, D. W.; PETERSON JR, J. P. The determination of uranium burnup in MWD/ton. Pleaianton, Calif., General Electric Co., Mar. 1960.
(GEAP-3373).
96. ROSZTOCZY. Z. R. & VALERINO, M. F. One-group three-dlmeniional analyilt of assembly wise power and exposure distributions on Yankee Core I. Trans. Am. nucl. Soc.. 2:135-6, 1966.
9 7 . ROTTER, W. Determination of burn-up of irradiated fual elements by pulsed neutron interrogation. Ann. nucl. Set. Engng., Jk461-8, 1974.
98. SAVAGE, D. J, & DRUMMOND, J. L. The separation of neodymhim for the determination of the burn-up of nuclear fuels. Dunreay, Scotland, United Kingdom Atomic Energy Authority, Reactor Group, Apr. 1967. (TRG Report-1498D).
99. SCHACHTER, L; POPA, P.; HACMAN, D.; Absolute determination and axial radial distribution of burn-up for reactor lattice cells. Rev. roum. Phyt, |£(7):777B1, 1970.
100. SCHWOERER, F. fuel cycle costs in the 1980s: a forecast Nucl. tnergy Dig., 2 32-5, 1975.
101. SITES, J. R. & MELTON, C. E. Fission products: Stable Isotope Rnearch and Production Division semianual progress report for ending May 20, 1964. Oak RIdga Tann. Oak Ridge National Lab.,
1954. p.23-4. (ORNL-1732, Rev).
102. SITES, J. R.; GILPATRICK, L. O.; HARRISON, C. F.; ROBENSTOCK, H. M. Isotope - dilution method of analysis. In: KEIM, C. P. Stable isotope nnaarch and production division:
semiannual progress report for period ending November 20, 1954. Oak Ridge, Tenn., Oak Ridge National Laboratory, Feb. 1956. p. 19-20. (ORNL-1B29 (Del.)).
103. SMUD buys yallowcake, finds no sign of tight market. Nucleonics Week, §(50):1, Dec. 1967.
104. SUICH, J. E. & HONECK, H. C. The HAMMER system: tuHmngeneous analysis by multlgroup methods of exponential and reactors. Alken, 8. C , Savannah River Lab., Jan. 1967. (DP-1064).
105. TASAKA, K. & SASAM0T0, N. Measurement of burnup of Irradiated fual by analysis of gamma-ray spectra. In: INTERNATIONAL ATOMIC ENERGY AGENCY. Panel on fission product nuclear data, Bologna, X30Nov 1973, v.3. Vienna, 1974 p.71-82. (IAEA 169).
106. T Y R O R , J . G. Burn-up predictions for gas-cooled, graphite-moderated reactors. In:
INTERNATIONAL ATOMIC ENERGY AGENCY, Fuel bum-up predictions in thermal reactors: proceedings... 1967. Vienna, 1968. p.3-14.
107. TZOU, C. K. & YANG, C. M. Nondestructive burnup determination by gamma-ray spectroscopy.
Nucl. Techno/., 24(2):246-51. 1974.
108. WARD, A. G. Fuel burn-up and reactivity changes. In: INTERNATIONAL ATOMIC ENERGY AGENCY, Fuel burn-up predictions in thermal reactor»: proceedings... 1967. Vienna, 1968.
p. 15-27.
109. WEAST, R. C , ed. Handbook of chemistry and physics. 63. ed. Cleveland, Ohio, The Chemical Rubber Co., 1972/73. p.B-301, B-308, B-361, B-352, B-384.
110. WEST, D. B.; NEWTON, J. B.; GRANZZINI, E. D. Equipment and techniquM for gamma-scanning irradiated reactor fuel materials. In: AMERICAN NUCLEAR SOCIETY. Hot laboratories and equipment: proceedings of the eight conference on... held in San Francisco, California, December 13-15, 1960, v.2. Oak Ridge, Tann., U. 8. Atomic Energy Commission, |s.d.|.
p.391-8. (TID-7599).
111. ZYKOV, K. I. & MILLER, O. A. The problem of the buildup of fission products In fuel elements of the water-cooled-water-moderated power reactor type. Soclet atom. Energy., 39(3)517, 1975. ""