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

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.
Authors:
; ; ;
Publication Date:
OSTI Identifier:
491437
Report Number(s):
ORNL/TM-13077
ON: DE97006847; TRN: 97:012625
DOE Contract Number:
AC05-96OR22464
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Feb 1996
Research Org:
Oak Ridge National Lab., TN (United States)
Sponsoring Org:
USDOE Office of Energy Research, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
07 ISOTOPE AND RADIATION SOURCE TECHNOLOGY; 22 NUCLEAR REACTOR TECHNOLOGY; NEUTRON SOURCE FACILITIES; REACTOR SAFETY; REACTOR ACCIDENTS; DESIGN; HEAT TRANSFER; HYDRAULICS; FUEL ELEMENTS