Advanced neutron source reactor conceptual safety analysis report, three-element-core design: Chapter 15, accident analysis | Zendy

N.C.J. Chen | Zendy; M.W. Wendel | Zendy; G.L. Yoder | Zendy; R. M. Harrington | Zendy

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Advanced neutron source reactor conceptual safety analysis report, three-element-core design: Chapter 15, accident analysis

Author(s) -

N.C.J. Chen,

M.W. Wendel,

G.L. Yoder,

R. M. Harrington

Publication year - 1996

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/491437

Subject(s) - nuclear engineering , piping , core (optical fiber) , control rod , engineering , finite element method , nuclear reactor core , inner core , structural engineering , mechanical engineering , materials science , telecommunications , composite material

In order to utilize reduced enrichment fuel, the three-element-core design for the Advanced Neutron Source has been proposed. The proposed core configuration consists of inner, middle, and outer elements, with the middle element offset axially beneath the inner and outer elements, which are axially aligned. The three-element-core RELAP5 model assumes that the reactor hardware is changed only within the core region, so that the loop piping, heat exchangers, and pumps remain as assumed for the two-element-core configuration. To assess the impact of changes in the core region configuration and the thermal-hydraulic steady-state conditions, the safety analysis has been updated. This report gives the safety margins for the loss-of-off-site power and pressure-boundary fault accidents based on the RELAP5 results. AU margins are greater for the three-element-core simulations than those calculated for the two-element core

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