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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.”
Bojan Petrovic
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 438-443
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9222
Articles are hosted by Taylor and Francis Online.
The integral configuration of the International Reactor Innovative and Secure (IRIS) with its relatively thick downcomer region within the reactor vessel and compact spherical steel containment offers potential for a significant dose reduction but also presents challenges for the related deep-penetration shielding analyses due to the large spatial domain. It is necessary to determine the radiation field throughout the 25-m-diam spherical containment and into the adjoining auxiliary building.The shielding analysis is being performed using the "traditional" deterministic SN and Monte Carlo approaches and codes (TORT and MCNP, respectively). In the preliminary, scoping phase, the radiation field is sought "everywhere" throughout the power plant to identify any possible shielding issues. This is very challenging for typical Monte Carlo variance-reduction methods, which are devised and may work very well to provide results in a limited region or for individual "detectors" rather than everywhere. However, the recently developed FW-CADIS method, implemented within the MAVRIC sequence of the SCALE code system, aims to address this problem. It uses forward and adjoint deterministic SN calculations to generate effective biasing parameters for Monte Carlo simulations throughout the problem. Previous studies have confirmed its potential for obtaining Monte Carlo solutions with acceptable statistics over large spatial domains.The objective of this work was to evaluate the applicability of FW-CADIS/MAVRIC to efficiently perform the required shielding analysis of IRIS. For that purpose, a representative model was prepared, retaining the main problem characteristics, i.e., a large spatial domain (>10 m in each dimension) and significant attenuation (more than 12 orders of magnitude), but geometrically rather simplified at this stage of evaluation. The obtained preliminary results indicate that the FW-CADIS method implemented through the MAVRIC sequence in SCALE will enable determination of the radiation field throughout the large spatial domain of the IRIS nuclear power plant.
