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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Remembering ANS member Gil Brown
Brown
The nuclear community is mourning the loss of Gilbert Brown, who passed away on July 11 at the age of 77 following a battle with cancer.
Brown, an American Nuclear Society Fellow and an ANS member for nearly 50 years, joined the faculty at Lowell Technological Institute—now the University of Massachusetts–Lowell—in 1973 and remained there for the rest of his career. He eventually became director of the UMass Lowell nuclear engineering program. After his retirement, he remained an emeritus professor at the university.
Sukesh Aghara, chair of the Nuclear Engineering Department Heads Organization, noted in an email to NEDHO members and others that “Gil was a relentless advocate for nuclear energy and a deeply respected member of our professional community. He was also a kind and generous friend—and one of the reasons I ended up at UMass Lowell. He served the university with great dedication. . . . Within NEDHO, Gil was a steady presence and served for many years as our treasurer. His contributions to nuclear engineering education and to this community will be dearly missed.”
J. J. Ritts, M. Solomito, P. N. Stevens
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 246-258
Technical Paper | Radiation | doi.org/10.13182/NT71-A30889
Articles are hosted by Taylor and Francis Online.
Improved multicollision neutron fluence-to-dose conversion factors have been calculated for a phantom exposed to neutrons with energies from 15 MeV down to thermal. The phantom was a 30-cm-thick slab composed of the 11 most common elements in the standard man. The calculations consisted of the simultaneous solution of the neutron and secondary gamma-ray transport problem with the ANISN computer code for both a beam source and an isotropic flux source, and for a slab having both infinite and finite transverse dimensions. The fluence-to-dose conversion factors were based on new neutron fluence-to-kerma factors and improved secondary gamma-ray yields determined for the individual elements comprising the slab. The neutron and gamma-ray cross sections used in the calculations are from the ENDF/B file and the OGRE library, respectively.
