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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.”
B. T. Rearden
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 367-382
Technical Paper | doi.org/10.13182/NSE03-03
Articles are hosted by Taylor and Francis Online.
Methodologies to calculate adjoint-based first-order-linear perturbation theory sensitivity coefficients with multigroup Monte Carlo methods are developed, implemented, and tested in this paper. These techniques can quickly produce sensitivity coefficients for all nuclides and reaction types for each region of a system model. Monte Carlo techniques have been developed to calculate the neutron flux moments and/or angular fluxes necessary for the generation of the scattering terms of the sensitivity coefficients.The Tools for Sensitivity and Uncertainty Analysis Methodology Implementation in three dimensions (TSUNAMI-3D) control module has been written for the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system implementing this methodology. TSUNAMI-3D performs automated multigroup cross-section processing and then generates the forward and adjoint neutron fluxes with an enhanced version of the KENO V.a Monte Carlo code that implements the flux moment and angular flux calculational techniques. Sensitivity coefficients are generated with the newly developed Sensitivity Analysis Module for SCALE (SAMS). Results generated with TSUNAMI-3D compare favorably with results generated with direct perturbation techniques.
