Investigating the TEPC radiation quality factor response for low energy accelerator based clinical applications

Radiation Protection Dosimetry

Volumn 103, Issue 4, 2003, Pages 311-322

  Aslam, A ^a   Prestwich, W V ^a   McNeill, F E ^a   Waker, A J ^b  

^a MCMASTER UNIVERSITY   (Canada)

^b ATOMIC ENERGY OF CANADA LIMITED   (Canada)

Author keywords

[No Author keywords available]

Indexed keywords

PROPANE;

ALGORITHM; CLINICAL PRACTICE; CONTROLLED STUDY; IN VIVO STUDY; INTERMETHOD COMPARISON; MATHEMATICAL COMPUTING; NEUTRON ACTIVATION ANALYSIS; NEUTRON DOSIMETER; NEUTRON DOSIMETRY; NEUTRON RADIATION; PROPORTIONAL COUNTER; RADIATION DETECTOR; RADIATION ENERGY; RADIATION FIELD; REVIEW; SIMULATION; TISSUE EQUIVALENT PROPORTIONAL COUNTER;

EID: 0038137162     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/oxfordjournals.rpd.a006148     Document Type: Review

References (64)

1. Palmer, H. E., Nelp, W. B., Murano, R. and Rich, C. The feasibility of in vivo neutron activation analysis of total body calcium and other elements of body composition. Phys. Med. Biol. 13(2), 269-279 (1968).
2. Chamberlain, M. J., Fremlin, J. H., Holloway, I. and Peters, D. K. Use of the cyclotron for whole body neutron activation analysis: theoretical and practical considerations. Int. J. Appl. Radiat. Isot. 21, 725-734 (1970).
3. Boddy, K., Dennis, J. A. and Lawson, R. C. Neutron dosimetry in the in vivo measurement of intrathyroidal iodine in man by activation analysis. Phys. Med. Biol. 14(3), 471-480 (1969).
4. Boddy, K., Elliott, A., Robertson, I., Mahaffy, M. E. and Holloway, I. A high sensitivity dual-detector shadow-shield wholebody counter with an 'invariant' response for total body in vivo neutron activation analysis. Phys. Med. Biol. 20(2), 296-304 (1975).
5. Evans, H. J., Leblanc, A. D. and Johnson, P. C. Facility for regional in vivo neutron activation analysis of skeletal calcium. Phys. Med. Biol. 24, 181-187 (1979).
6. Cohn, S. H. The present state of in-vivo neutron activation analysis in clinical diagnosis, and therapy. At. Energ. Rev. 18(3), 599-660 (1980).
7. Beddoe, A. H., Zudmeer, H. and Hill, G. L. A prompt gamma in vivo neutron activation analysis facility for measurement of total body nitrogen in the critically ill. Phys. Med. Biol. 29, 371-383 (1984).
8. Heymsfield, S. B., Wang, J., Lichtman, S., Kamen, Y., Kehayias. J. and Pierson, R. N. Jr. Body composition in elderly subjects: A critical appraisal of clinical methodology. Am. J. Clin. Nutr. 50(5 Suppl), 1167-1175; 1231-1235 (1989).
9. Chettle, D. R. and Fremlin, J. H. Techniques of in vivo neutron activation analysis. Phys. Med. Biol. 29(9), 1011-1043 (1984).
10. Ellis, K. J. Human body composition: in vivo methods. Physiol Rev. 80(2), 649-80 (2000).
11. Ritchie, A. I. M. Neutron yields and energy spectra from thick target Li(p,n) source. J. Phys. D: Appl. Phys. 9, 15-26 (1976).
12. Meadows, J. W. Determination of the energy scale for neutron cross-section measurements employing a monoenergetic accelerator. ANL/TDM-25 (1977).
13. 7Be. At. Energ. 43, 947-949 (1977).
14. Clayton, C. G. and Spackman, S. Neutron intensity and energy distributions from protons in the energy range 1.95 MeV to 5.5 MeV incident on thick targets of lithium. Int. J. Appl. Radiat. Isot. 36(1), 13-50 (1985).
15. Yanch, J. C., Zhou, X. L., Shefer, R. E. and Klinkowstein, R. E. Acceleralor-based epithermal neutron beam design for neutron capture therapy. Med. Phys. 19(3), 709-721 (1992).
16. Allen, D. A. and Benyon, T. D. A design study for an accelerator-based epithermal neutron beam fr BNCT. Phys. Med. Biol. 40, 807-821 (1995).
17. Zhou, X. L. and Lee, C. Analysis of epithermal neutron production by near-threshold (p,n) reactions. Appl. Radiat. Isot. 48, 1571-1575 (1997).
18. Zhou, X. L. and Lee, C. Lithium compounds as targets for (p,n) reactions. Appl. Radiat. Isot. 48, 1493-1496 (1997).
19. 10B neutron capture enhancement of fast neutron irradiations. Med. Phys. 25(60), 885-891 (1998).
20. 7Be reaction and their application in selective activation analysis. Nucl. Instrum. Methods Phys. Res. B 139, 293-297 (1998).
21. Bayanov, B. F. and 14 others. Accelerator-based neutron source for the neutron-capture and fast neutron therapy at hospital. Nucl. Instrum. Methods Phys. Res. A 413(2-3), 397-426 (1998).
22. Powell, J. A., Ludewig, H., Todosow, M. and Reich, M. Target and filter concepts for accelerator-driven boron neutron capture therapy applications. Nucl. Tech. 125, 104-115 (1999).
23. 7 Be reaction near threshold. Nucl. Instrum. Methods Phys. Res. B 152, 1-11 (1999).
24. Arnold, M. L., McNeill F. E., Prestwich, W. V. and Chettle D. R. System design for in-vivo neutron activation analysis measurements of manganese in the human brain: based on Monte Carlo modeling. Appl. Radiat. Isot. 53, 651-656 (2000).
25. Arnold, M. L. Development of an accelerator based system for in vivo neutron activation analysis measurements of manganese in humans. PhD Thesis, McMaster University, Hamilton, ON, Canada (2000).
26. Palerme, S. Pilot studies for in-vivo bone aluminum measurements. MSc Thesis, McMaster University, Hamilton, ON, Canada (1993).
27. Pejovic-Milic, A. An accelerator-based in-vivo measurement of aluminum in human bone by neutron activation analysis. MSc Thesis, McMaster University, Hamilton, ON, Canada (1998).
28. Pejovic-Milic, A. In-vivo measurement of some trace elements in human bone. PhD Thesis, McMaster University, Hamilton, ON, Canada (2001).
29. Pejovic-Milic, A., McNeill, F. E., Prestwitch, W. V., Waker, A. J. and Chettle, D. R. Development of an accelerator-based determination of aluminum burden in peripheral bone by neutron activation analysis. Appl. Radiat. Isot. 49(5/6), 717-719 (1998).
30. Pejovic-Milic, A., Arnold, M. L., McNeill, F. E. and Chettle, D. R. Monte Carlo design study for in-vivo bone aluminum measurement using a low energy accelerator beam. Appl. Radiat. Isot. 53, 657-664 (2000).
31. Arnold, M. L., McNeill, F. E. and Chettle, D. R. The feasibility of measuring manganese concentrations in human liver using neutron activation analysis. NeuroToxicol. 20(2-3), 407-412 (1999).
32. Arnold, M. L., McNeill, F. E., Stronach, I. M., Waker, A. J., Pejovic-Milic, A. and Chettle D. R. An accelerator based system for in vivo neutron activation analysis measurements of manganese in human hand bones. Med. Phys. 29(11), 2718-2724 (2002).
33. Aslam, Prestwich, W. V., McNeill, F. E. and Waker, A. J. Spectrometry and dosimetry for low energy accelerator based in-vivo measurements. Annual Report McMaster Accelerator Laboratory, McMaster University, Hamilton, ON, Canada (2001).
34. Eisen, Y., Brake, R. J., Vasilik, D. G., Erkkila, B. H. and Littlejohn, G. J. The performance of low pressure tissue-equivalent chambers and a new method for parameterising the dose equivalent. Radiat. Prot. Dosim. 15(2), 117-130 (1986).
35. Dietze, G. and 10 others. Intercomparison of dose equivalent meters based on microdosimetric techniques. Radiat. Prot. Dosim. 23(1/4), 227-234 (1988).
36. Alberts, W. G., Dietze, E., Guldbakke, S., Kluge, H. and Schuhmacher, H. International intercomparison of TEPC systems used for radiation protection. Radiat. Prot. Dosim. 29, 47-53 (1989).
37. 3He gas mixtures. Radiat. Prot. Dosim. 29(1-2), 113-118 (1989).
38. Gerdung, S., Grillmaier, R. E., Lim, T., Pihet, P., Schuhmacher, H. and Ségur, P. Performance of TEPCs at low pressures: some attempts to improve their dose equivalent response in the neutron energy range from 10 keV to 1 MeV. Radiat. Prot. Dosim. 52(1-4), 57-59 (1994).
39. Waker, A. J. Principles of experimental microdosimetry. Radiat. Prot. Dosim. 61(4), 297-308 (1995).
40. Khaloo, R. and Waker, A. J. An evaluation of hydrogen as a TEPC counting gas in radiation protection microdosimetry. Radiat. Prot. Dosim. 58(3), 185-191 (1995).
41. Taylor, G. C. An analytical correction for the TEPC dose equivalent response problem. Radiat. Prot. Dosim. 61(1-3), 67-70 (1995).
42. Nunomiya, T., Kim, E., Kurosawa, T., Taniguchi, S., Yonai, S., Nakamura, T., Nakane, Y., Sakamoto, Y. and Tanaka, S. Measurement of lineal-energy distributions for neutrons of 8 keV to 65 MeV by using a tissue-equivalent proportional counter. Radiat. Prot. Dosim. 102(1), 49-59 (2002).
43. ICRP. Recommendations of the ICRP. Ann. ICRP 1(3). ICRP Publication 26 (Oxford: Pergamon Press) (1977).
44. ICRP. Radiation protection recommendation of the International Commission on Radiological Protection. ICRP Publication 60 (Oxford: Pergamon Press) (1991).
45. ICRU. The quality factor in radiation protection. ICRU Report 40 (Bethesda, MD: ICRU Publications) (1986).
46. 204Tl. PhD Thesis, McMaster University, Hamilton, ON, Canada (1982).
47. Srdoc, D. and Marino, S. A. Microdosimetry of monoenergelic neutrons. Radiat. Res. 146(4), 466-474 (1996).
48. ICRU. Stopping powers and ranges for protons and alpha particles. ICRU Report 49 (Bethesda, MD: ICRU Publications) (1983).
49. ICRU. Microdosimetry. ICRU Report 36 (Bethesda, MD: ICRU Publications) (1983).
50. Knoll, G. F. Radiation detection and measurement. 2nd Edn (New York: Wiley) (1989).
51. Folkerts, K. H., Menzel, H. G., Schuhmacher H. and Arend, E. TEPC radiation protection dosimetry in the environment of accelerators and at nuclear facilities. Radiat. Prot. Dosim. 23(1-4), 261-264 (1988).
52. Kawecka, B., Morstin, K. and Booz, J. Optimization of the design of microdosimetric dose equivalent meters. Radiat. Prot. Dosim. 9(3), 203-206 (1984).
53. Kadachi, A., Waheed, A., Al-Eshaikh, M. and Obeid, M. Use of photodiode in microdosimetry and evaluation of effective quality factor. Nucl. Instrum. Methods Res. A 404(2-3), 400-406 (1998).
54. Baum, J., Kuehner, V. and Chase, R. Dose equivalent meter designs based on tissue equivalent proportional counters. Health Phys. 19, 813-824 (1970).
55. Stinchcomb, T. G. and Borak, T. B. Neutron quality parameters versus energy below 4 MeV from microdosimetric calculations. Radiat. Res. 93(1), 1-18 (1983).
56. Townsend, W., Wilson, J. and Cucinotta, F. Simple parameterization for quality factors as a function of linear energy transfer. Health Phys. 53(5), 531-532 (1987).
57. Evans, R. D. The atomic nucleus (New York: McGraw-Hill) (1955).
58. Endo, S. and 12 others. Neutron generator at Hiroshima university for use in radiobiology study. J. Radiat. Res. (Tokyo) 36(2), 91-102 (1995).
59. Endo, S., Hoshi, M., Takada, J., Tauchi, H., Matsuura, S., Takeoka, S., Kitagawa, K., Suga, S. and Komatsu, K. Neutron generator (HIRRAC) and dosimetry study. J. Radiat. Res. (Tokyo) 40(Suppl.) 14-20 (1999).
60. 7Be*. At. Data Nucl. Data Tables 15, 57-84 (1975).
61. Attix, F. H. Introduction to radiological physics and radiation dosimetry. (New York: Wiley) (1986).
62. Press. W. H., Teukolsky, S. A., Vetterling, W. T. and Flannery, B. P. Numerical recipes in FORTRAN 77: the art of scientific computing. 2nd edn, Vol. 1. In: FORTRAN numerical recipes (Cambridge University Press) (1992).
63. Wagner, S. R., Grosswendt, B., Harvey, J. R., Mill, A. J., Selbach, H. J. and Siebert, B. R. L. Unified conversion functions for the ICRU operational radiation protection quantities. Radiat. Prot. Dosim. 12(2), 231-235 (1985).
64. Dietze, G. and Siebert, B. R. Photon and neutron dose contributions and mean quality factors phantoms of diffirent size irradiated by monoenergetic neutrons. Radiat. Res. 140(1), 130-133 (1994).