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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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.
Tsutomu Yokoyama, Toshiyuki Tamura
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 372-388
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26304
Articles are hosted by Taylor and Francis Online.
Calculations have been made to investigate the dependence of the primary neutron emission rate (the neutron source strength) of spent boiling water reactor (BWR) fuel assemblies on the irradiation parameters: initial 235U enrichment, void fraction, power density, and operation history. A BWR lattice cell calculation code, which was verified by experiments, has been used to calculate the buildup of transuranium isotopes. The neutron emission rate was split into three components: 242Cm, 244Cm, and other nuclides. The effects of the irradiation parameters have been studied for each of the three components. The energy spectra of the primary neutrons emitted by the irradiated fuel have been calculated parametrically. The calculations have elucidated the neutron emission characteristics of the spent BWR fuel assemblies and provided the basic information to be used for:1. the neutron-shielding design for spent-fuel storage facilities and transportation casks2. the feasibility study of the startup of a BWR without radioisotope neutron source3. the application of passive neutron method to the nondestructive determination of burnup and plutonium contents in spent BWR fuels.
