Томас Маклафлин - Обзор ядерных аварий с возникновением СЦР (LA-13638)

• Название: Обзор ядерных аварий с возникновением СЦР (LA-13638)
• Автор: Томас Маклафлин
• Издательство: Лос-Аламосская национальная лаборатория
• Жанр: Физика
• Год: 2003

Обсуждаются ядерные аварии с возникновением самоподдерживающейся цепной реакции (СЦР) и характеристики разгона на мгновенных нейтронах на критических сборках. Рассмотрено 60 аварий на различного типа оборудовании и установках. Приводятся детали, позволяющие читателю понять физическую картину, химические процессы во время аварии, а также предоставляется информация об административной обстановке на промежутке времени, предшествующем возникновению аварии, в тех случаях, когда она доступна. Приводится картина изменения мощности во времени, приводятся данные об энерговыделении, последствиях и причинах аварии. Для описания тех аварийных ситуаций, которые возникли на промышленных предприятиях, в настоящую версию были включены два новых раздела. В первом из них содержится анализ и выводы о физических и ядерно-физических свойствах систем, в которых происходила цепная реакция. Во втором обобщаются наблюдения и обсуждаются извлеченные уроки. Обсуждение случаев резкого превышения мощности крупных энергетических реакторов не включено в данный отчет.

---

Второй тип активной зоны SPERT I 93 (стержни UO2 в воде, обогащение урана 4 %) испытывался в течение 1963 г. и 1964 г. Эксперименты по изучению переходных процессов с такой активной зоной показали действенность эффекта Доплера в самогашении и создали основу для анализа аварий подобных энергетических реакторов. Две попытки разрушить активную зону путем вывода реактора на очень короткие периоды (2,2 и 1,55 миллисекунд) были неудачными. В каждом случае эффект Доплера оказывался эффективным, и дополнительное гашение развивалось потому, что один или два топливных тонких стрежня (из нескольких сотен) трескался и вызывал локальное кипение. Считалось, что тонкие стержни были насыщены водой перед испытанием.

Литература

1. W. R. Stratton, "A Review of Criticality Accidents," Los Alamos Scientific Laboratory report LA-3611 (September 1967).

2. W. R. Stratton, revised by D. R. Smith, "A Review of Criticality Accidents," Lawrence Livermore National Laboratory report DOE/NCT-04 (March 1989).

3. H. C. Paxton, "Glossary of Nuclear Criticality Terms," Los Alamos National Laboratory report LA-11627-MS (October 1989).

4. F. Y. Barbry, "SILENE Reactor: Results of Selected Typical Experiments," CEA Institut de Protection et de Surete Nucleaire, Departement de Recherches en Securite, Centre d'Etudes de VALDUC, Service de Recherches en Surete et Criticite Report SRSC no223 (September 1994).

5. P. Lecorche and R. L. Seale, "Review of the Experiments Performed to Determine the Radiological Consequences of a Criticality Accident," Oak Ridge Y-12 Plant report Y-CDC-12 (November 1973).

6. M. S. Dunenfeld and R. K. Stitt, "Summary Review of the Kinetics Experiments on Water Boilers," Atomics International, North American Aviation, Inc. report NAA-SR-7087 (February 1963).

7. F. S. Patton, et al., "Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958," Oak Ridge Y-12 Plant report Y-1234 (July 1958).

8. A. D. Callihan and J. T. Thomas, "Accidental Radiation Excursion at the Oak Ridge Y-12 Plant — I, Description and Physics of the Accident," Health Physics 1, 363–372 (1959).

9. "Oak Ridge Y-12 Accidental Excursion, June 16, 1958," Nucleonics 16 (11), 138–140, 200–203 (November 1958).

10. G. S. Hurst, R. H. Ritchie, and L. C. Emerson, "Accidental Radiation Excursion at the Oak Ridge Y-12 Plant — III, Determination of Radiation Doses," Health Physics 2, 121–133 (1959).

11. H. C. Paxton, R. D. Baker, W. J. Maraman, and R. Reider, "Nuclear Critical Accident at the Los Alamos Scientific Laboratory on December 30, 1958," Los Alamos Scientific Laboratory report LAMS-2293 (February 1959).

12. H. C. Paxton, R. D. Baker, W. J. Maraman, and R. Reider, "Los Alamos Criticality Accident, December 30, 1958," Nucleonics 17 (4), 107–108, 151–153 (April 1959).

13. W. L. Ginkel, et al., "Nuclear Incident at the Idaho Chemical Processing Plant on October 16, 1959," Phillips Petroleum Company, Atomic Energy Division report IDO-10035 (February 1960).

14. R. C. Paulus, et al., "Nuclear Incident at the Idaho Chemical Processing Plant on January 25, 1961," Phillips Petroleum Company, Atomic Energy Division report IDO-10036 (June 1961).

15. J. W. Latchum, F. C. Haas, W. M. Hawkins, and F. M. Warzel, "Nuclear Incident at the Idaho Chemical Processing Plant of January 25, 1961," Phillips Petroleum Company report LA—54—61A, (April 1961).

16. A. R. Olsen, R. L. Hooper, V. O. Uotinen, and C. L. Brown, "Empirical Model to Estimate Energy Release from Accidental Criticality," Transactions of the American Nuclear Society 19, 189–191 (October 1974).

17. D. L. Hetrick, letter to Thomas McLaughlin (14 July 1999).

18. A. D. Callihan, "Accidental Nuclear Excursion in Recuplex Operation at Hanford in April 1962," Nuclear Safety 4 (4), 136–144 (June 1963).

19. E. D. Clayton, "Further Considerations of Criticality in Recuplex and Possible Shutdown Mechanism," Hanford Atomic Products Operation report HW—77780 (May 1963).

20. C. N. Zangar, "Summary Report of Accidental Nuclear Excursion, Recuplex Operation, 234-5 Facility," Richland Operations Office, U. S. Atomic Energy Commission report TID—18431 (1962).

21. C. N. Zangar, et al., "Final Report of Accidental Nuclear Excursion, Recuplex Operation, 234-5 Facility," Hanford Operations Office report HW—74723 (August 1962).

22. E. D. Clayton, "The Hanford Pulser Accident," Transactions of the American Nuclear Society 46, 463–464 (June 1984).

23. F. R. Nakache and M. M. Shapiro, "The Nuclear Aspects of the Accidental Criticality at Wood River Junction, Rhode Island, July 24, 1964," United Nuclear Corporation report TID-21995 (November 1964).

24. H. Kouts, et al., "Report of the AEC Technical Review Committee," United States Atomic Energy Commission (November 1964).

25. J. T. Daniels, H. Howells, and T. G. Hughes, "Criticality Incident — Aug 24, 1970, Windscale Works," Transactions of the American Nuclear Society 14, 35–36 (June 1971).

26. M. C. Evans, "A Review of Criticality Accidents Within the European Community," Transactions of the American Nuclear Society 46, 462–463 (June 1984).

27. M. C. Evans, "A Review of Criticality Accidents Within the European Community," supplemental material presented at the 1984 Annual Meeting of the American Nuclear Society, New Orleans, Louisiana (June 1984).

28. "Recovery of ICPP from Criticality Event of October 17, 1978, Part II, Support and Safety Justification of the Specific Approach to Emptying H-100," Allied Chemical, Idaho Chemical Programs report ACI—366 (January 1979).

29. "ICPP Criticality Event of October 17, 1978," Nuclear Safety 21 (5), 648–653 (October 1980).

30. R. E. Wilson and W. D. Jensen, "Reflections on the 1978 ICPP Criticality Accident," in Proceedings of the Sixth International Conference on Nuclear Criticality Safety, Versailles, Vol. 4, pp. 1540–1544 (September 1999).

31. "Report of the Uranium Processing Plant Criticality Accident Investigation Committee," The Uranium Processing Plant Criticality Accident Investigation Committee of The Nuclear Safety Commission (December 1999).

32. H. Mizuniwa, et al., "Dose Evaluation to Workers at JCO Criticality Accident Based on Whole Body Measurement of Sodium—24 Activity and Area Monitoring" (in Japanese), Journal of the Japanese Nuclear Power Association 43 (1), 56–66 (January 2001).

33. F. R. McCoy, III, T. P. McLaughlin, and L. C. Lewis, "Trip Report of Visit to Tokyo and Tokai-mura, Japan, on October 18–19, 1999, for Information Exchange with Government of Japan Concerning the September 30, 1999 Tokai-mura Criticality Accident," U. S. Department of Energy (November 1999).

34. J. B. Briggs, Editor, International Handbook of Evaluated Criticality Safety Benchmark

Experiments, Nuclear Energy Agency, NEA/NSC/DOC(95)-03 (September 2002).

35. H. C. Paxton and N. L. Pruvost, "Critical Dimensions of Systems Containing 235U, 239Pu, and 233U, 1986 Revision," Los Alamos National Laboratory report LA-10860-MS (July 1987).

36. E. F. Taylor and J. A. Wheeler, Spacetime Physics (W. H. Freeman and Co., San Francisco), p. 60 (1966).

37. A. D. Callihan, W. J. Ozeroff, H. C. Paxton, and C. L. Schuske, "Nuclear Safety Guide," U. S. Atomic Energy Commission report TID-7016 (1957).

38. D. F. Hayes, "A Summary of Accidents and Incidents Involving Radiation in Atomic Energy Activities, June 1945 through December 1955," U. S. Atomic Energy Commission report TID—5360 (August 1956).

39. L. D. P. King, "Design and Description of Water Boiler Reactors," in Proceedings of the International Conference on Peaceful Uses of Atomic Energy, Geneva, Vol. 2, pp. 372–391 (August 1955).

40. B. R. Leonard, Jr., "A Study of the Radiation Burst in the Hanford Homogeneous Reactor," Hanford Works report HW—24327 (May 1952).

41. J. T. Thomas and A. D. Callihan, "Radiation Excursions at the ORNL Critical Experiments Laboratory, I— May 26, 1954, II— February 1, 1956," Oak Ridge National Laboratory report ORNL-2452 (May 1958).

42. H. C. Paxton, "Booby Traps," Los Alamos Scientific Laboratory report AECD-4240 (June 1957).

43. A. D. Callihan, "Excursion at the Oak Ridge Critical Experiments Facility, January 30, 1968," Oak Ridge National Laboratory report ORNL-TM-2207 (January 1968).

44. H. C. Paxton, "Critical-Assembly Booby Traps," Nucleonics 16 (3), 80–81 (March 1958).

45. R. W. Paine, Jr., et al., "A Study of an Accidental Radiation Burst," Los Alamos Scientific Laboratory report LA—1289 (March 1951).

46. E. C. Mallary, G. E. Hansen, G. A. Linenberger, and D. P. Wood, "Neutron Burst from a Cylindrical Untamped Oy Assembly," Los Alamos Scientific Laboratory report LA—1477 (July 1952).

47. R. E. Peterson and G. A. Newby, "An Unreflected U-235 Critical Assembly," Nuclear Science and Engineering 1 (2), 112–125 (May 1956).

48. T. F. Wimett, et al., "Time Behavior of Godiva Through Prompt Critical," Los Alamos Scientific Laboratory report LA—2029 (April 1956).

49. H. C. Paxton, "Godiva, Topsy, Jezebel — Critical Assemblies at Los Alamos," Nucleonics 13 (10), 48–50 (October 1955).

50. A. M. Voinov, S. V. Vorontsov, V. T. Punin, and I. G. Smirnov, "Criticality accidents at VNIIEF," in Proceedings of the Sixth International Conference on Nuclear Criticality Safety, Versailles, Vol. 2, pp. 874–887 (September 1999).

51. А. М. Воинов и др., "Стенд для исследования нейтронно-физических характеристик простых критических сборок", ВАНТ, серия Физика ядерных реакторов, вып. 2, с. 21–29, 1992 г.

52. H. C. Paxton, "Godiva Wrecked at Los Alamos," Nucleonics 15 (4), 104 (April 1957).

53. W. R. Stratton, T. H. Colvin, and R. B. Lazarus, "Analysis of Prompt Excursions in Simple Systems and Idealized Fast Reactors," in Proceedings of the Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva, Vol. 12, pp. 196–206 (September 1958).

54. T. F. Wimett, and J. D. Orndoff, "Applications of Godiva II Neutron Pulses," in Proceedings of the Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva, Vol. 10, pp. 449–460 (September 1958).

55. A. D. Callihan, "Criticality Excursion of November 10, 1961," Oak Ridge National Laboratory report ORNL-TM-139 (February 1962).

56. М. И. Кувшинов и др., "Экспериментальные исследования связанных систем, содержащих импульсный реактор БИР и подкритическую сборку", ВАНТ, cерия Импульсные реакторы и простые критические сборки, № 2, с. 3—15, 1988 г.

57. R. L. Kathren, W. C. Day, D. H. Denham, and J. L. Brown, "Health Physics Following a Nuclear Excursion: The LRL Incident of 26 March, 1963," Lawrence Radiation Laboratory report UCRL-7345, Rev. 1 (June 1963).

58. P. D. O'Brien, "Fast Burst Reactor Operational Incidents," in Proceedings of the National Topical Meeting on Fast Burst Reactors, Albuquerque, NM, (U. S. Atomic Energy Commission), pp. 373–384 (January 1969).

59. V. A. Teryokhin, V. D. Perezhogin, and Yu. A. Sokolov, "Criticality Measurements at VNIITF — Review," in Proceedings of the Fifth International Conference on Nuclear Criticality Safety, Albuquerque, NM, Vol. 1, pp. 4.44—4.47 (September 1995).

60. N. P. Voloshin, I. S. Pogrebov, and V. A. Teryokhin, "RFNC–VNIITF Physical Experimental

Division and a Short Historical Sketch of Critical Mass Measurements," in Proceedings of the Fifth International Conference on Nuclear Criticality Safety, Albuquerque, NM, Vol. 1, pp. P.31—P.36 (September 1995).

61. A. H. Kazi, H. G. Dubyoski, and R. W. Dickinson, "Preoperational Test Experience with the Army Pulse Radiation Facility Reactor," in Proceedings of the National Topical Meeting on Fast Burst Reactors, Albuquerque, NM (U. S. Atomic Energy Commission), pp. 353–371 (January 1969).

62. Н. П. Волошин, "По материалам заключения комиссии о причинах ядерной аварии в РФЯЦ-ВНИИЭФ в г. Сарове", Атомпресса, № 26 (262), июль 1997 г.

63. В. Т. Пунин, И. Г. Смирнов, С. А. Зыков, "Авария на стенде критических сборок в РФЯЦ-ВНИИЭФ", Атомная энергия, том 83, вып. 2, с. 154–156, август 1997 г.

64. Г. Ф. Ходалев и др., "Доза облучения экспериментатора при аварии на критической сборке в РФЯЦ-ВНИИЭФ", Атомная энергия, том 85, вып. 2, с. 153–158, август 1998 г.

65. H. F. McFarland, Controlled Nuclear Chain Reaction: The First 50 Years (American Nuclear Society, La Grange Park, IL), pp. 52–54 (1992).

66. D. G. Hurst and A. G. Ward, "Canadian Research Reactors," in Progress in Nuclear Energy, Series II, REACTORS (Pergamon Press, London), Vol. 1, pp. 1—48 (1956).

67. R. O. Brittan, R. J. Hasterlik, L. D. Marinelli, and F. W. Thalgott, "Technical Review of ZPR-1 Accidental Transient — The Power Excursion, Exposures, and Clinical Data," Argonne National Laboratory report ANL-4971 (January 1953).

68. W. B. Lewis, "The Accident to the NRX Reactor on December 12, 1952," Atomic Energy of Canada Ltd. report DR-32 (July 1953).

69. W. J. Henderson, A. C. Johnson, and P. R. Tunnicliffe, "An Investigation of Some of the Circumstances Pertinent to the Accident to the NRX Reactor of December 12, 1952," Atomic Energy of Canada Ltd. report NEI-26 (March 1953).

70. J. R. Dietrich, et al., "Experimental Investigation of the Self-limitation of Power During Reactivity Transients in a Subcooled, Water-moderated Reactor, Borax-I Experiments, 1954," Argonne National Laboratory report ANL-5323 (1954).

71. "Reactors, Operational Power Reactors," Nucleonics 13 (9), 40–45 (September 1955).

72. J. R. Dietrich, "Experimental Determinations of the Self-regulation and Safety of Operating Water-moderated Reactors," in Proceedings of the United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva, Vol. 13, pp. 88—101 (August 1955).

73. J. R. Dietrich and D. C. Layman, "Transient and Steady State Characteristics of a Boiling Reactor, The Borax Experiments, 1953," Argonne National Laboratory report AECD-3840 (February 1954).