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Title: LIFE Materails: Molten-Salt Fuels Volume 8

Abstract

The goals of the Laser Inertial Fusion Fission Energy (LIFE) is to use fusion neutrons to fission materials with no enrichment and minimum processing and have greatly reduced wastes that are not of interest to making weapons. Fusion yields expected to be achieved in NIF a few times per day are called for with a high reliable shot rate of about 15 per second. We have found that the version of LIFE using TRISO fuel discussed in other volumes of this series can be modified by replacing the molten-flibe-cooled TRISO fuel zone with a molten salt in which the same actinides present in the TRISO particles are dissolved in the molten salt. Molten salts have the advantage that they are not subject to radiation damage, and hence overcome the radiation damage effects that may limit the lifetime of solid fuels such as TRISO-containing pebbles. This molten salt is pumped through the LIFE blanket, out to a heat exchanger and back into the blanket. To mitigate corrosion, steel structures in contact with the molten salt would be plated with tungsten or nickel. The salt will be processed during operation to remove certain fission products (volatile and noble and semi-noble fission products),more » impurities and corrosion products. In this way neutron absorbers (fission products) are removed and neutronics performance of the molten salt is somewhat better than that of the TRISO fuel case owing to the reduced parasitic absorption. In addition, the production of Pu and rare-earth elements (REE) causes these elements to build up in the salt, and leads to a requirement for a process to remove the REE during operation to insure that the solubility of a mixed (Pu,REE)F3 solid solution is not exceeded anywhere in the molten salt system. Removal of the REE will further enhance the neutronics performance. With molten salt fuels, the plant would need to be safeguarded because materials of interest for weapons are produced and could potentially be removed.« less

Authors:
; ; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
956850
Report Number(s):
LLNL-TR-409526
TRN: US1005010
DOE Contract Number:  
W-7405-ENG-48
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; CORROSION PRODUCTS; FISSION; FISSION PRODUCTS; FUSION YIELD; HEAT EXCHANGERS; MOLTEN SALT FUELS; MOLTEN SALTS; NEUTRON ABSORBERS; SOLID FUELS; SOLID SOLUTIONS; MATERIALS

Citation Formats

Moir, R, Brown, N, Caro, A, Farmer, J, Halsey, W, Kaufman, L, Kramer, K, Latkowski, J, Powers, J, Shaw, H, and Turchi, P. LIFE Materails: Molten-Salt Fuels Volume 8. United States: N. p., 2008. Web. doi:10.2172/956850.
Moir, R, Brown, N, Caro, A, Farmer, J, Halsey, W, Kaufman, L, Kramer, K, Latkowski, J, Powers, J, Shaw, H, & Turchi, P. LIFE Materails: Molten-Salt Fuels Volume 8. United States. doi:10.2172/956850.
Moir, R, Brown, N, Caro, A, Farmer, J, Halsey, W, Kaufman, L, Kramer, K, Latkowski, J, Powers, J, Shaw, H, and Turchi, P. Thu . "LIFE Materails: Molten-Salt Fuels Volume 8". United States. doi:10.2172/956850. https://www.osti.gov/servlets/purl/956850.
@article{osti_956850,
title = {LIFE Materails: Molten-Salt Fuels Volume 8},
author = {Moir, R and Brown, N and Caro, A and Farmer, J and Halsey, W and Kaufman, L and Kramer, K and Latkowski, J and Powers, J and Shaw, H and Turchi, P},
abstractNote = {The goals of the Laser Inertial Fusion Fission Energy (LIFE) is to use fusion neutrons to fission materials with no enrichment and minimum processing and have greatly reduced wastes that are not of interest to making weapons. Fusion yields expected to be achieved in NIF a few times per day are called for with a high reliable shot rate of about 15 per second. We have found that the version of LIFE using TRISO fuel discussed in other volumes of this series can be modified by replacing the molten-flibe-cooled TRISO fuel zone with a molten salt in which the same actinides present in the TRISO particles are dissolved in the molten salt. Molten salts have the advantage that they are not subject to radiation damage, and hence overcome the radiation damage effects that may limit the lifetime of solid fuels such as TRISO-containing pebbles. This molten salt is pumped through the LIFE blanket, out to a heat exchanger and back into the blanket. To mitigate corrosion, steel structures in contact with the molten salt would be plated with tungsten or nickel. The salt will be processed during operation to remove certain fission products (volatile and noble and semi-noble fission products), impurities and corrosion products. In this way neutron absorbers (fission products) are removed and neutronics performance of the molten salt is somewhat better than that of the TRISO fuel case owing to the reduced parasitic absorption. In addition, the production of Pu and rare-earth elements (REE) causes these elements to build up in the salt, and leads to a requirement for a process to remove the REE during operation to insure that the solubility of a mixed (Pu,REE)F3 solid solution is not exceeded anywhere in the molten salt system. Removal of the REE will further enhance the neutronics performance. With molten salt fuels, the plant would need to be safeguarded because materials of interest for weapons are produced and could potentially be removed.},
doi = {10.2172/956850},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2008},
month = {12}
}

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