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Title: Neutronics and activation analysis of lithium-based ternary alloys in IFE blankets

Journal Article · · Fusion Engineering and Design
 [1];  [2];  [3];  [3];  [3];  [1]
  1. Univ. of California, Berkeley, CA (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  3. TerraPower, Bellevue, WA (United States)

Here we report that an attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that it has very high tritium solubility and results in very low levels of tritium permeation throughout the facility infrastructure. However, lithium metal vigorously reacts with air and water and presents plant safety concerns. The Lawrence Livermore National Laboratory is carrying an effort to develop a lithium-based alloy that maintains the beneficial properties of lithium (e.g. high tritium breeding and solubility) and at the same time reduces overall flammability concerns. This study evaluates the neutronics performance of lithium-based alloys in the blanket of an inertial fusion energy chamber in order to inform such development. 3-D Monte Carlo calculations were performed to evaluate two main neutronics performance parameters for the blanket: tritium breeding ratio (TBR), and the fusion energy multiplication factor (EMF). It was found that elements that exhibit low absorption cross sections and higher q-values such as lead, tin, and strontium, perform well with those that have high neutron multiplication such as lead and bismuth. These elements meet TBR constrains ranging from 1.02 to 1.1. However, most alloys do not reach EMFs greater than 1.15. Additionally, it was found that enriching lithium significantly increases the TBR and decreases the minimum lithium concentration by more than 60%. The amount of enrichment depends on how much total lithium is in the alloy to begin with. Alloys that performed well in the TBR and EMF calculations were considered for activation analysis. Activation simulations were executed with 50 years of irradiation and 300 years of cooling. It was discovered that bismuth is a poor choice due to achieving the highest decay heat, contact dose rates, and accident doses. In addition, it does not meet the waste disposal ratings (WDR). Some of the activation results for alloys with tin, zinc, and gallium were in the higher end and should be considered secondary to elements such as strontium and barium that had overall better results. The results of this study along with other considerations such as thermodynamics, and chemical reactivity will help down select a preferred lithium ternary alloy.

Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC52-07NA27344; 14-ERD-035
OSTI ID:
1262171
Alternate ID(s):
OSTI ID: 1360840
Report Number(s):
LLNL-JRNL-677168; 14-ERD-035
Journal Information:
Fusion Engineering and Design, Vol. 107, Issue C; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 4 works
Citation information provided by
Web of Science

References (31)

Chamber Design for the Laser Inertial Fusion Energy (LIFE) Engine journal July 2011
Lithium alloy chemical reactivity with reactor materials: current state of knowledge journal April 1991
Review of blanket designs for advanced fusion reactors journal December 2008
Design and R&D progress of Korean HCCR TBM journal October 2014
Overview of Helium Cooled Ceramic Reflector Test Blanket Module development in Korea journal October 2013
New progress on design and R&D for solid breeder test blanket module in China journal October 2014
Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan journal August 2012
Present status of the conceptual design of the EU test blanket systems journal October 2011
Recent research and development for the dual-coolant blanket concept in the US journal December 2008
Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER journal October 2007
Design status and development strategy of China liquid lithium–lead blankets and related material technology journal August 2007
Preliminary design of a helium cooled molten lithium test blanket module for the ITER test in Korea journal June 2007
Blanket/first wall challenges and required R&D on the pathway to DEMO journal November 2015
The National Ignition Facility and the Promise of Inertial Fusion Energy journal July 2011
Timely Delivery of Laser Inertial Fusion Energy (LIFE) journal July 2011
Toward the ultimate goal of tritium self-sufficiency: Technical issues and requirements imposed on ARIES advanced power plants journal December 2009
Blanket Optimization Studies for the Hylife Inertial Confinement Fusion Reactor journal November 1985
Parameter Study of an Inertial Fusion Energy Chamber Response Using the 1-D BUCKY Radiation Hydrodynamics Code journal October 2014
Initial MCNP6 Release Overview journal December 2012
ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology journal December 2006
LIFE Tritium Processing: A Sustainable Solution for Closing the Fusion Fuel Cycle journal August 2013
Activation Analysis for a He/LiPb Dual Coolant Blanket for DEMO Reactor journal August 2011
Re-evaluation of the use of low activation materials in waste management strategies for fusion journal November 2000
Initial Integration of Accident Safety, Waste Management, Recycling, Effluent, and Maintenance Considerations for Low-Activation Materials journal January 1991
Selection of IFE target materials from a safety and environmental perspective
  • Latkowski, J. F.; Sanz, J.; Reyes, S.
  • Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 464, Issue 1-3 https://doi.org/10.1016/S0168-9002(01)00079-1
journal May 2001
Accident Safety Comparison of Elements to Define Low-Activation Materials journal July 1990
Thermodynamic Assessment of the Ternary Alloy System Li-SN-ZN report April 2014
Comparison of lithium and the eutectic lead-lithium alloy, two candidate liquid metal breeder materials for self-cooled blankets journal March 1995
Polonium-210 as a poison journal March 2007
Polonium Issue in Fast Reactor Lead Coolants and One of the Ways of Its Solution conference March 2009
The Hazards of Cobalt journal January 1977

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