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- Radiation shielding
- Radiation Shielding
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- NRE 6759: Radiation Shielding Principles and Computations
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Textbooks: J. Shultis and R. Instructors: Nolan E. Hertel References: N. Schaeffer ed. Lewis and W. Miller, Jr.
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NRE 6759: Radiation Shielding Principles and Computations
Nuclear Energy pp Cite as. A quantity describing how neutrons or photons incident on the surface of some medium e. 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. A general term for the energy transferred from radiation to matter.
Handbook of Nuclear Engineering pp Cite as. This chapter deals with shielding against nonionizing radiation, specifically gamma rays and neutrons with energies less than about 10 MeV, and addresses the assessment of health effects from exposure to such radiation. The chapter begins with a discussion of how to characterize mathematically the energy and directional dependence of the radiation intensity and, similarly, the nature and description of radiation sources. What follows is a discussion of how neutrons and gamma rays interact with matter and how radiation doses of various types are deduced from radiation intensity and target characteristics. The chapter concludes with a discussion of shielding materials, radiological assessments, and risk calculations. The authors of this chapter gratefully acknowledge the guidance and support of their colleagues and mentors in the field of radiation shielding and radiation protection.
This paper presents the set of procedures developed in Radiation Protection Measurements Laboratory at National Centre for Nuclear Research for evaluation of shielding properties of high performance concrete. The purpose of such procedure is to characterize the material behaviour against gamma and neutron radiation. The shielding properties against photons were evaluated using Cs and 60 Co sources. The neutron radiation measurements have been performed by measuring the transmitted radiation from PuBe source. Scattered neutron radiation has been evaluated using the shadow cone technique. A set up of ionization chambers was used during all experiments. The gamma dose was measured using C-CO 2 ionization chamber.
Radiation Shielding and. Radiological Protection. J. Kenneth Shultis ⋅ Richard E. Faw. Department of Mechanical and Nuclear Engineering, Kansas.
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