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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
R. G. Alsmiller, Jr., J. Barish
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 378-388
Technical Paper | doi.org/10.13182/NSE79-A19956
Articles are hosted by Taylor and Francis Online.
Multigroup cross sections (47 n groups, 21 gamma-ray groups) in ANISN format for neutron energies from thermal to 60 MeV and for the elements hydrogen, 10B, 11B, carbon, oxygen, silicon, calcium, chromium, iron, and nickel are described. A P5 Legendre expansion is used at energies , and a P3 Legendre expansion is used at energies . Below 14.9 MeV, the cross sections are from the Radiation Shielding Information Center's fusion energy cross-section library. Above this energy, differential elastic scattering cross-section data from optical model calculations are used, and differential nonelastic scattering data from the intranuclear-cascade-evaporation model are used. Calculated results of the dose equivalent versus depth in the shield from a point isotropic source at the center of a 366-cm-thick spherical shell heavy concrete (density = 3.6 g cm−3) shield are presented. The energy distribution of the source neutrons is approximately that from a Li(D, n) neutron radiation damage facility.