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Radiation Shielding

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Nuclear Energy

Abstract

We live in a world that abounds in radiation of all types. Many radiations, such as the neutrinos or visible light from our sun present little risk to us. Other radiations, such as medical x-rays or gamma rays emitted by radioactive materials, have the potential to cause us harm. In this entry, only the transport of indirectly ionizing radiation is considered. These radiations consist of chargeless particles such as neutrons or photons that, upon interacting with matter, produce energetic secondary charged particles called directly ionizing radiation. It is these secondary charged particles that, through ionization and excitation of ambient atoms along their paths, cause radiation damage to biological tissues or other sensitive materials.

This chapter was originally published as part of the Encyclopedia of Sustainability Science and Technology edited by Robert A. Meyers. DOI:10.1007/978-1-4419-0851-3

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Abbreviations

Albedo:

A quantity describing how neutrons or photons incident on the surface of some medium (e.g., a wall) are reflected or reemitted from the surface.

Buildup factor:

A factor to account for production of secondary photons in a shield. The transmitted dose from only uncollided photons times the buildup factor equals the dose from all photons, uncollided plus secondary photons.

Dose:

A general term for the energy transferred from radiation to matter. Specifically, the absorbed dose is the amount of energy imparted to matter from ionizing radiation in a unit mass of that matter. Units are the gray (Gy) and rad, respectively, equivalent to 1 J/kg and 100 ergs/g.

Flux:

A measure of the intensity of a radiation field. Specifically, it equals the number of radiation particles entering, in a unit time, a sphere of cross-sectional area \( \Delta A \) divided by \( \Delta A \), as \( \Delta A \to 0 \). The flux, integrated over a specified time interval is called the fluence.

Interaction coefficient:

A quantity, denoted by \( \mu \), describing how readily a photon or neutron interacts with a given medium. Specifically, it is the probability a radiation particle of energy E will interact in a specified manner per unit distance of travel, for infinitesimal distances. It thus has units of inverse length. The total interaction coefficient \( \mu = \sum\nolimits_i {\mu_i} \) where \( {\mu_i} \) is the coefficient for the ith type of interaction (e.g., scattering, absorption).

Neutron:

A neutral subatomic particle that collectively with positively charged protons forms an atomic nucleus. Although both are composite particles composed of quarks and gluons, for the energies considered in this entry they can be viewed as fundamental unchangeable particles.

Photon:

A quantum of electromagnetic radiation with energy \( E = h\nu \), where h is Planck’s constant and \( \nu \) is the frequency. Photons produced by a change in the structure of the nucleus are called gamma photons and those produced by atomic electron rearrangement are called x-rays.

Skyshine:

A term for the radiation that reaches some point of interest after being scattered by the atoms in the atmosphere back to the point of interest.

Transport equation:

Also known as the linearized Boltzmann equation, it describes rigorously the spatial, energy, and angular distribution of neutrons or photons in any medium with arbitrary source distributions. From its solution, the radiation flux or dose anywhere in the medium can be determined.

Bibliography

Primary Literature

  1. Shultis JK, Faw RE (2005) Radiation shielding technology. Health Phys 88:297–322

    Article  Google Scholar 

  2. Mutscheller A (1925) Physical standards of protection against Roentgen-ray dangers. Am J Roentgenol Radiat Ther 13:65–70

    Google Scholar 

  3. National Council on Radiation Protection and Measurements (1941) Safe handling of radioactive luminous compounds. NBS handbook 27. NCRP report 5. US Government Printing Office, Washington, DC

    Google Scholar 

  4. Blizard EP, Abbott LS (eds) (1962) Reactor handbook, vol III, Part B, Shielding. Wiley, New York

    Google Scholar 

  5. Jaeger RH (ed) (1968) Engineering compendium on radiation shielding, vol 1, Shielding fundamentals and methods. Springer, New York

    Google Scholar 

  6. Haffner JW (1967) Radiation and shielding in space. Academic, New York

    Google Scholar 

  7. Shure K (1964) P-3 multigroup calculations of neutron attenuation. Nucl Sci Eng 19:310

    Google Scholar 

  8. National Council on Radiation Protection and Measurements (1971) Protection against neutron radiation. NCRP report 38. National Council on Radiation Protection and Measurements, Washington, DC

    Google Scholar 

  9. National Council on Radiation Protection and Measurements (1976) Structural shielding design and evaluation for medical use of x-rays and gamma rays of energies up to 10 MeV. NCRP report 49. National Council on Radiation Protection and Measurements, Washington, DC

    Google Scholar 

  10. Kocher DC (1981) Radioactive decay tables. Technical Information Center, U.S. Department of Energy; DOE/TIC 11026, Washington, DC

    Google Scholar 

  11. Weber DA, Eckerman KE, Dillman LT, Ryman JC (1989) MIRD: radionuclide data and decay schemes. Society of Nuclear Medicine, Medical Internal Radiation Dose Committee, New York

    Google Scholar 

  12. ANS (American Nuclear Society) (1991) American national standard gamma-ray attenuation coefficients and buildup factors for engineering materials. ANSI/ANS-6.4.3-1991. American Nuclear Society, La Grange Park

    Google Scholar 

  13. Caswell RS, Coyne JJ, Randolph ML (1980) Kerma factors for neutron energies below 30 MeV. Radiat Res 83:217–254

    Article  Google Scholar 

  14. International Commission on Radiological Protection (1987) Data for use in protection against external radiation. Publication 51. Annals of the ICRP 17(2/3). Pergamon, Oxford

    Google Scholar 

  15. International Commission on Radiological Protection (1996) Conversion coefficients for use in radiological protection against external radiation. Publication 74. Annals of the ICRP 26(3/4). Pergamon, Oxford

    Google Scholar 

  16. Adams ML, Larsen EW (2002) Fast iterative methods for discrete-ordinates particle transport calculations. Prog Nucl Energy 40(1):3–159

    Article  Google Scholar 

  17. Shultis JK, Faw RE (2000) Radiation shielding. American Nuclear Society, La Grange Park

    Google Scholar 

  18. Rockwell T III (ed) (1956) Reactor shielding design manual. Van Nostrand, Princeton

    Google Scholar 

  19. Schaeffer NM (1973) Historical background. In: Schaeffer NM (ed) Reactor shielding. TID-25951. US Atomic Energy Commission, Washington, DC

    Google Scholar 

  20. Hirayama H (1987) Exposure buildup factors of high-energy gamma rays for water, concrete, iron, and lead. Nucl Technol 77:60–67

    Google Scholar 

  21. Faw RE, Shultis JK (1993) Absorbed dose buildup factors in air for 10–100 MeV photons. Nucl Sci Eng 114:76–80

    Google Scholar 

  22. Fano U, Spencer LV, Berger MJ (1959) Penetration and diffusion of x rays. In: Encyclopedia of physics, vol 38, Part 2. Springer, Berlin

    Google Scholar 

  23. Goldstein H (1959) Fundamental aspects of reactor shielding. Addison-Wesley, Reading

    Google Scholar 

  24. Spencer LV (1962) Structure shielding against fallout radiation from nuclear weapons. Monograph 42. National Bureau of Standards, Washington, DC

    Google Scholar 

  25. Takeuchi K, Tanaka S, Kinno M (1981) Transport calculation of gamma rays including bremsstrahlung by the discrete ordinates code PALLAS. Nucl Sci Eng 78:273–283

    Google Scholar 

  26. Takeuchi K, Tanaka S (1984) Buildup factors of gamma rays, including bremsstrahlung and annihilation radiation for water, concrete, iron, and lead. Nucl Sci Eng 87:478–489

    Google Scholar 

  27. Negin CA, Worku G (1998) Microshield v.5 user’s manual. Grove Software, Lynchburg

    Google Scholar 

  28. Malenfant RE (1967) QAD: a series of point kernel general-purpose shielding programs. LA-3573. Los Alamos National Laboratory, Los Alamos

    Google Scholar 

  29. Price JH et al (1979) Utilization instructions for QADMOD-G. RRA-N7914. Radiation Research Association, Fort Worth. Available from RSICC as CCC565/QADMOD-GP

    Google Scholar 

  30. Litwin KA et al (1994) Improvements to the point kernel code QAD-CGGP: a code validation and user’s manual. RC-1214 COG-94-65. AECL Research, Canada. Available from RSICC as CCC-645/QAD-CGGP-A

    Google Scholar 

  31. Malenfant RE (1990) \( {G^3} \): a general purpose gamma-ray scattering code. LA-5176. Los Alamos National Laboratory, Los Alamos. Available from RSICC as CCC-564/G33-GP

    Google Scholar 

  32. Archer BR (1995) History of the shielding of diagnostic x-ray facilities. Health Phys 69:750–758

    Article  Google Scholar 

  33. Simpkin DJ (1989) Shielding requirements for constant-potential diagnostic x-ray beams determined by a Monte Carlo calculation. Health Phys 56:151–154

    Article  Google Scholar 

  34. Archer BR, Conway BJ, Quinn PW (1994) Attenuation properties of diagnostic x-ray shielding materials. Med Phys 21:1499–1507

    Article  Google Scholar 

  35. Simpkin DJ (1995) Transmission data for shielding diagnostic x-ray facilities. Health Phys 68:704–709

    Article  Google Scholar 

  36. Chilton AB (1971) Effect of material composition on neutron penetration of concrete slabs. Report 10425. National Bureau of Standards, Washington, DC

    Google Scholar 

  37. Roussin RW, Schmidt FAR (1971) Adjoint Sn calculations of coupled neutron and gamma-ray transport through concrete slabs. Nucl Eng Des 15:319–343

    Article  Google Scholar 

  38. Roussin RW, Alsmiller RG Jr, Barish J (1973) Calculations of the transport of neutrons and secondary gamma rays through concrete for incident neutrons in the energy range 15 to 75 MeV. Nucl Eng Des 24:250–257

    Article  Google Scholar 

  39. Wyckoff JM, Chilton AB (1973) Dose due to practical neutron energy distributions incident on concrete shielding slabs. Proceedings of 3rd international congress IRPA, American Nuclear Society, La Grange Park

    Google Scholar 

  40. Wang X, Faw RE (1995) Transmission of neutrons and secondary gamma rays through concrete slabs. Radiat Prot Dosim 60:212–222

    Google Scholar 

  41. Chilton AB, Huddleston CM (1963) A semi-empirical formula for differential dose albedo for gamma rays on concrete. Nucl Sci Eng 17:419–424

    Google Scholar 

  42. Chilton AB, Davisson CM, Beach LA (1965) Parameters for C-H albedo formula for gamma rays reflected from water, concrete, iron, and lead. Trans Am Nucl Soc 8:656

    Google Scholar 

  43. Chilton AB (1967) A modified formula for differential exposure albedo for gamma rays reflected from concrete. Nucl Sci Eng 27:481–482

    Google Scholar 

  44. Brockhoff RC (2003) Calculation of albedos for neutrons and photons. Ph.D. dissertation, Department of Mechanical and Nuclear Engineering, Kansas State University, Manhattan

    Google Scholar 

  45. Selph WE (1973) Albedos, ducts, and voids. In: Schaeffer NM (ed) Reactor shielding. TID-25951. US Atomic Energy Commission, Washington, DC

    Google Scholar 

  46. Simmons GL, Albert TE, Gritzner DM (1979) The SAI/EPRI information library. Report SAI-013-79-525-LJ. Science Applications Inc, La Jolla

    Google Scholar 

  47. Cain VR, Emmett MV (1979) BREESE-II: auxiliary routines for implementing the albedo option in the MORSE Monte Carlo code. ORNL/TM-6807. Oak Ridge National Laboratory, Oak Ridge

    Google Scholar 

  48. Maerker RE, Muckenthaler FJ (1966) Measurements and single-velocity calculations of differential angular thermal-neutron albedos for concrete. Nucl Sci Eng 26:339

    Google Scholar 

  49. Coleman WA, Maerker RE, Muckenthaler FJ, Stevens PJ (1967) Calculation of doubly differential current albedos for epicadmium neutrons incident on concrete and comparison of the subcadmium component with experiment. Nucl Sci Eng 27:411–422

    Google Scholar 

  50. Chandrasekhar S (1960) Radiative transfer. Dover, New York

    Google Scholar 

  51. Wells MB (1964) Reflection of thermal neutrons and neutron capture gamma rays from concrete. USAEC report RRA-M44. Radiation Research Associates, Fort Worth

    Google Scholar 

  52. Gomes IC, Stevens PN (1991) MORSE/STORM: a generalized albedo option for Monte Carlo calculations. ORNL/FEDC-91/1, TN. Oak Ridge National Laboratory, Oak Ridge

    Google Scholar 

  53. LeDoux JC, Chilton AB (1959) Gamma ray streaming through two-legged rectangular ducts. Nucl Sci Eng 11:362–368

    Google Scholar 

  54. National Council on Radiation Protection and Measurements (2003) Radiation protection for particle accelerator facilities. NCRP report 144. National Council on Radiation Protection and Measurements, Washington, DC

    Google Scholar 

  55. Lampley CM, Andrews MC, Wells MB (1988) The SKYSHINE-III procedure: calculation of the effects of structure design on neutron, primary gamma-ray, and secondary gamma-ray dose rates in air. RRA-T8209A. Radiation Research Associates, Fort Worth

    Google Scholar 

  56. Lampley CM (1979) The SKYSHINE-II procedure: calculation of the effects of structure design on neutron, primary gamma-ray, and secondary gamma-ray dose rates in air. RRA-T7901. Radiation Research Associates, Fort Worth

    Google Scholar 

  57. Brockhoff RC, Shultis JK, Faw RE (1996) Skyshine line-beam response functions for 20- to 100-MeV photons. Nucl Sci Eng 123:282–288

    Google Scholar 

  58. Gui AA, Shultis JK, Faw RE (1997) Response functions for neutron skyshine analysis. Nucl Sci Eng 125:111–127

    Google Scholar 

  59. Shultis JK, Faw RE, Bassett MS (1991) The integral line-beam method for gamma skyshine analysis. Nucl Sci Eng 107:228–245

    Google Scholar 

  60. Stedry MH (1994) A Monte Carlo line-beam calculation of gamma-ray skyshine for shielded sources. MS thesis, Kansas State University, Manhattan

    Google Scholar 

  61. Negin CA (1987) The microskyshine manual. Grove Software, Lynchburg

    Google Scholar 

  62. Carlson BG, Lathrop KD (1968) Transport theory, the method of discrete ordinates. In: Greenspan H, Kelber CN, Okrent D (eds) Computing methods in reactor physics. Gordon and Breach, New York

    Google Scholar 

  63. Duderstadt JJ, Martin WR (1979) Transport theory. Wiley, New York

    MATH  Google Scholar 

  64. Lewis EE, Miller WF (1984) Computational methods of neutron transport theory. Wiley, New York

    Google Scholar 

  65. Rhoades WA, Childs RL (1987) The TORT three-dimensional discrete ordinates neutron/photon transport code. ORNL-6268. Oak Ridge National Laboratory, Oak Ridge

    Google Scholar 

  66. Alcouffe RE, Baker RS, Dahl JA, Turner SA (2002) PARTISN user’s guide. CCS-4, LA-UR-02-5633. Los Alamos National Laboratory, Transport Methods Group, Los Alamos

    Google Scholar 

  67. Goertzel G, Kalos MH (1958) Monte Carlo methods in transport problems. In: Progress in nuclear energy, ser 1, vol 2. Pergamon, New York

    Google Scholar 

  68. Kalos MH (1968) Monte Carlo integration of the adjoint gamma-ray transport equation. Nucl Sci Eng 33:284–290

    Google Scholar 

  69. Kalos MH, Nakache NR, Celnik JC (1968) Monte Carlo methods in reactor computations. In: Greenspan H, Kelber CN, Okrent D (eds) Computing methods in reactor physics. Gordon and Breach, New York

    Google Scholar 

  70. Spanier J, Gelbard EM (1969) Monte Carlo principles and neutron transport problems. Addison-Wesley, Reading

    MATH  Google Scholar 

  71. Carter LL, Cashwell ED (1975) Particle-transport simulation with the Monte Carlo method. TID-26607. Los Alamos National Laboratory, Los Alamos

    Google Scholar 

  72. Lux I, Koblinger LK (1991) Monte Carlo particle transport methods: neutron and photon calculations. CRC Press, Boca Raton

    Google Scholar 

  73. Dunn WL, Shultis JK (2011) Exploring the Monte Carlo method. Elsevier, Amsterdam

    Google Scholar 

  74. Jenkins TM, Nelson TM, Rindi A (1988) Monte Carlo transport of electrons and photons. Plenum, New York

    Book  Google Scholar 

  75. Nelson WR, Hirayama H, Rogers DWO (1985) The EGS4 code system. SLAC-265. Stanford Linear Accelerator Center, Menlo Park

    Google Scholar 

  76. Halbleib JA, Kensek RP, Mehlhorn TA, Valdez GD, Seltzer SM, Berger MJ (1992) ITS Version 3.0: the integrated TIGER series of coupled electron/photon Monte Carlo transport codes. SAND91-1634. Sandia National Laboratories, Albuquerque

    Google Scholar 

  77. X-5 Monte Carlo Team (2003) MCNP—a general Monte Carlo n-particle transport code, version 5. LA-UR-03-1987 (vol 1: Overview and theory), LA-UR-03-0245 (vol 2: User’s guide). Los Alamos National Laboratory, Los Alamos

    Google Scholar 

Books and Reviews

  • Blizard EP, Abbott LS (eds) Reactor handbook, vol 3, Part B, Shielding. Wiley, New York

    Google Scholar 

  • Faw RE, Shultis JK (1999) Radiological assessment: sources and doses. American Nuclear Society, La Grange Park

    Google Scholar 

  • Goldstein H (1959) Fundamental aspects of reactor shielding. Addison-Wesley, Reading

    Google Scholar 

  • Haffner JW (1967) Radiation and shielding in space. Academic, New York

    Google Scholar 

  • ICRP (2007) The 2007 recommendations of the international commission on radiological protection. Report 103. Annals of the ICRP 37:2–4

    Google Scholar 

  • ICRP (2008) Nuclear decay data for dosimetric calculations. Report 107. Annals of the ICRP 38(3):1–96

    Google Scholar 

  • ICRU (1993) Quantities and units in radiation protection dosimetry. Report 51. International Commission on Radiation Units and Measurements, Bethesda

    Google Scholar 

  • ICRU (1998) Fundamental quantities and units for ionizing radiation. Report 60. International Commission on Radiation Units and Measurements, Bethesda

    Google Scholar 

  • Jaeger RG (ed) (1968–1975) Engineering compendium on radiation shielding. Shielding materials and design, vol 1; Shielding materials and designs, vol 2; Shield design and engineering, vol 3. Springer, New York

    Google Scholar 

  • NCRP (2003) Radiation protection for particle accelerator facilities. Report 144. National Council on Radiation Protection and Measurements, Bethesda

    Google Scholar 

  • NCRP (2005) Structural shielding design for medical x-ray imaging facilities. Report 147. National Council on Radiation Protection and Measurements, Bethesda

    Google Scholar 

  • NCRP (2005) Structural shielding design and evaluation for megavoltage x- and gamma-ray radiotherapy facilities. Report 151. National Council on Radiation Protection and Measurements, Bethesda

    Google Scholar 

  • Rockwell T III (ed) (1956) Reactor shielding design manual. Van Nostrand, Princeton

    Google Scholar 

  • Schaeffer NM (ed) (1973) Reactor shielding. TID-25951, U.S. Atomic Energy Commission, Washington, DC

    Google Scholar 

  • Shultis JK, Faw RE (2000) Radiation shielding. American Nuclear Society, La Grange Park

    Google Scholar 

  • UN (1977, 1982, 1988, 1993, 2000) Reports of the United Nations Scientific Committee on the Effects of Atomic Radiation, New York. http://www.unscear.org/unscear/en/publications.html

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Shultis, J.K., Faw, R.E. (2013). Radiation Shielding. In: Tsoulfanidis, N. (eds) Nuclear Energy. Springer, New York, NY. https://doi.org/10.1007/978-1-4614-5716-9_14

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