Fast neutron fluence evaluation of the smart reactor pressure vessel by using the geoshield code

Kyo Youn Kim, Kang Seog Kim, Ha Yong Kim, Chung Chan Lee, Sung Quun Zee

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

In Korea, the design of an advanced integral reactor system called SMART has been developed by KAERI to supply energy for seawater desalination as well as an electricity generation. A fast neutron fluence distribution at the SMART reactor pressure vessel was evaluated to confirm the integrity of the vessel by using the GEOSHIELD code. The GEOSHIELD code was developed by KAERI in order to prepare an input list including a geometry modeling of the DORT code and to process results from the DORT code output list. Results by a GEOSHIELD code processing and by a manual processing of the DORT show a good agreement.

Original languageEnglish
Title of host publicationCanadian Nuclear Society - 28th Annual Conference of the Canadian Nuclear Society and 31st CNS/CNA Student Conference 2007
Subtitle of host publication"Embracing the Future: Canada's Nuclear Renewal and Growth"
Pages509-516
Number of pages8
StatePublished - 2007
Externally publishedYes
Event28th Annual Conference of the Canadian Nuclear Society and 31st CNS/CNA Student Conference 2007: "Embracing the Future: Canada's Nuclear Renewal and Growth" - Saint John, N.B., Canada
Duration: Jun 3 2007Jun 6 2007

Publication series

NameCanadian Nuclear Society - 28th Annual Conference of the Canadian Nuclear Society and 31st CNS/CNA Student Conference 2007: "Embracing the Future: Canada's Nuclear Renewal and Growth"
Volume1

Conference

Conference28th Annual Conference of the Canadian Nuclear Society and 31st CNS/CNA Student Conference 2007: "Embracing the Future: Canada's Nuclear Renewal and Growth"
Country/TerritoryCanada
CitySaint John, N.B.
Period06/3/0706/6/07

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