Steam-explosion safety considerations for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory
This report provides a perspective on steam-explosion safety and design issues for the Advanced Neutron Source (ANS) reactor being designed at the Oak Ridge National Laboratory. A historical background along with a description of experiments and analytical work performed to date has been provided. Preliminary analyses (for the ANS) have been conducted to evaluate steam-explosion pressure- pulse loadings, the effects of reactor coolant system (RCS) overpressurization, and slug energetics. The method used for pressure-pulse magnitude evaluation was benchmarked with previous calculations, an aluminum-water steam-explosion experiment, and test reactor steam explosion data with good agreement. Predicted pressure-pulse magnitudes evaluated were found to be several orders of magnitude lower than corresponding values evaluated by correlating available energies with shock-wave pressures from equivalent chemical detonations. The preliminary best estimate, as well as conservative estimates for RCS volume-pressurization failure and slug energetics for RCS volume-pressurization failure and slug energetics, indicated that (1) steam explosions in the ANS have significant damage potential, and (2) steam-explosion issues must be considered during the design phase of the ANS Project. Recommendations are made for efficiently addressing this important safety and design issue. 38 refs., 17 figs., 11 tabs.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Org:
- Country of Publication:
- United States
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; RESEARCH REACTORS; REACTOR ACCIDENTS; STEAM; EXPLOSIONS; DESIGN; FAILURE MODE ANALYSIS; HEAT TRANSFER; HYDRAULICS; ORNL; PRESSURIZING; REACTIVITY; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RECOMMENDATIONS; ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; MECHANICS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; US AEC; US DOE; US ERDA; US ORGANIZATIONS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors
Enter terms in the toolbar above to search the full text of this document for pages containing specific keywords.