Showing papers by "James J. Sienicki published in 1999"

Fundamental demonstration of natural circulation feasibility for an HLMC reactor

Abstract: Concepts are being developed and evaluated at Argonne National Laboratory for a smaller nuclear steam supply system with proliferation-resistant features targeted for export to developing countries. Specific features of interest here include low reactor power [300 MW(thermal)]; utilization of inert heavy-liquid-metal coolant (HLMC), namely, lead-bismuth eutectic (T{sub mp} = 125 C), eliminating concerns over metal-water reactions; 15-yr core lifetime, enabling access to fissile materials to be restricted by design; and reliance on purely natural-circulation coolant heat transport, eliminating primary system coolant pumps. Evaluation of this concept is being carried out in stages. The stage 1 investigations to which the results presented in this paper belong are directed at establishing the basic feasibility of the concept through the application of first-principles analyses. This approach is warranted while detailed aspects of the core design are yet to be determined. The objective of the present work is to demonstrate at a fundamental level the feasibility of utilizing natural-circulation coolant heat transport with the HLMC.

Thermal-hydraulic development a small, simplified, proliferation-resistant reactor.

Abstract: This paper addresses thermal-hydraulics related criteria and preliminary concepts for a small (300 MWt), proliferation-resistant, liquid-metal-cooled reactor system. A main objective is to assess what extent of simplification is achievable in the concepts with the primary purpose of regaining economic competitiveness. The approach investigated features lead-bismuth eutectic (LBE) and a low power density core for ultra-long core lifetime (goal 15 years) with cartridge core replacement at end of life. This potentially introduces extensive simplifications resulting in capital cost and operating cost savings including: (1) compact, modular, pool-type configuration for factory fabrication, (2) 100+% natural circulation heat transport with the possibility of eliminating the main coolant pumps, (3) steam generator modules immersed directly in the primary coolant pool for elimination of the intermediate heat transport system, and (4) elimination of on-site fuel handling and storage provisions including rotating plug. Stage 1 natural circulation model and results are presented. Results suggest that 100+% natural circulation heat transport is readily achievable using LBE coolant and the long-life cartridge core approach; moreover, it is achievable in a compact pool configuration considerably smaller than PRISM A (for overland transportability) and with peak cladding temperature within the existing database range for ferritic steel with oxide layer surface passivation. Stage 2 analysis follows iteration with core designers. Other thermal hydraulic investigations are underway addressing passive, auxiliary heat removal by air cooling of the reactor vessel and the effects of steam generator tube rupture.