Thermal-hydraulic analysis of the LANL/IPPE/EDO-GP 1-MW LBE target
The accelerator-driven transmutation of waste (ATW) concept has been proposed by the United States and other countries to transmute plutonium, higher actinides, and other environmentally hazardous fission products. One of the key components in the ATW concept is a target that, via spallation, produces neutrons to transmute nuclear waste. Since significant heat is generated during fissioning of the waste actinides, an efficient heat removal system is necessary. Liquid lead-bismuth eutectic (LBE) is an efficient coolant as well as a good spallation target for production of neutrons. The LBE coolant technology has been successfully used in Russian submarine nuclear reactors. The International Science and Technology Center (ISTC) has funded the Institute of Physics and Power Engineering (IPPE) and the Experiment and Design Organization-Gidropress (EDO-GP) of Russia to design and manufacture a pilot target (Target Circuit One-TC1) that incorporates Russian LBE technology into the ATW concept. The target will be tested in the 800-MeV, 1-mA proton beam at the Los Alamos National Laboratory (LANL) in 2 yr. These target experiments will provide valuable information on the performance of LBE as both spallation target and coolant. They will also help to design target/blanket systems for future ATW facilities. In summary, the authors have carried out thermal-hydraulic analyses for the LANL/IPPE/EDO-GP 1-MW LBE target. It is shown that the current design is suitable for the beam-on tests. The diffuser plate successfully enhances the coolant flow around the window center but still avoids generating recirculation zone downstream. The temperature range is within the proper operation range for both the LBE coolant and the structural materials.
- Research Organization:
- Los Alamos National Lab., NM (US)
- OSTI ID:
- 20086959
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 82; Conference: 2000 Annual Meeting - American Nuclear Society, San Diego, CA (US), 06/04/2000--06/08/2000; Other Information: PBD: 2000; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACCELERATOR DRIVEN TRANSMUTATION
ACCELERATOR FACILITIES
TARGETS
COOLANTS
LIQUID METALS
LEAD ALLOYS
BISMUTH ALLOYS
SUBCRITICAL ASSEMBLIES
COOLING SYSTEMS
HEAT TRANSFER
HYDRAULICS