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Title: Neutronics Calculations for a Hypothetical Plasma-Jet-Driven Magneto-Inertial-Fusion Reactor

Abstract

We present neutronics calculations for a hypothetical fusion reactor based on the repetitively pulsed concept of plasma-jet-driven magneto-inertial fusion (PJMIF). A PJMIF reactor is envisioned to have a replaceable, 3-m-radius spherical metal first wall exposed to 14.1-MeV neutrons, a fast-flowing FLiBe liquid blanket (with thickness 0.75 m) behind the first wall serving as the primary coolant and tritium-breeding medium, and finally an outer structural spherical wall shielded by the blanket. Cylindrical penetrations through both walls and the flowing blanket allow for hundreds of plasma-gun drivers to inject hypersonic plasma jets that form both the DT plasma target and high-Z spherically imploding plasma liner to compress the target. This research is the first to conduct Monte Carlo N Particle (MCNP6.2) and CINDER2008 neutronics calculations relevant to the PJMIF reactor configuration, with the primary objectives of (1) determining the neutron flux as a function of blanket thickness in the blanket and key reactor components and (2) the tritium production rate in the liquid blanket. These results will be used to estimate other quantities of interest, such as first-wall and gun-electrode lifetimes based on DPA accumulation, optimum blanket thickness, activation level of the outer wall and xenon liner, and achievable tritium-breeding ratios. Energymore » dependent flux tallies were used to calculate neutron flux inside the FLiBe blanket and outer wall, as well as the cylindrical ports where plasma guns are located. Tally multipliers of the flux in MCNP6.2 estimated tritium breeding ratio, DPA, and nuclear heating, while the depletion code CINDER2008 was used to compare tritium breeding ratios with MCNP6.2 and calculate activation of the outer wall and xenon liner. These calculations provide a baseline for blanket requirements necessary for power production in a PJMIF reactor.« less

Authors:
ORCiD logo [1];  [1];  [2]; ORCiD logo [1];  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. HyperJet Fusion Corp., Chantilly, VA (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Programs (DP) (NA-10)
OSTI Identifier:
1574753
Report Number(s):
LA-UR-19-21042
Journal ID: ISSN 1536-1055
Grant/Contract Number:  
89233218CNA000001
Resource Type:
Accepted Manuscript
Journal Name:
Fusion Science and Technology
Additional Journal Information:
Journal Volume: 75; Journal Issue: 6; Journal ID: ISSN 1536-1055
Publisher:
American Nuclear Society
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Neutronics; MCNP; CINDER; Plasma Jet; PJMIF; Plasma Liner; Magneto-inertial fusion; advanced fusion concepts

Citation Formats

Rolison, Lucas Matthew, Fensin, Michael Lorne, Thio, Yong C. Francis, Hsu, Scott C., and Cruz, Edward Jeffrey. Neutronics Calculations for a Hypothetical Plasma-Jet-Driven Magneto-Inertial-Fusion Reactor. United States: N. p., 2019. Web. doi:10.1080/15361055.2019.1613140.
Rolison, Lucas Matthew, Fensin, Michael Lorne, Thio, Yong C. Francis, Hsu, Scott C., & Cruz, Edward Jeffrey. Neutronics Calculations for a Hypothetical Plasma-Jet-Driven Magneto-Inertial-Fusion Reactor. United States. doi:10.1080/15361055.2019.1613140.
Rolison, Lucas Matthew, Fensin, Michael Lorne, Thio, Yong C. Francis, Hsu, Scott C., and Cruz, Edward Jeffrey. Fri . "Neutronics Calculations for a Hypothetical Plasma-Jet-Driven Magneto-Inertial-Fusion Reactor". United States. doi:10.1080/15361055.2019.1613140. https://www.osti.gov/servlets/purl/1574753.
@article{osti_1574753,
title = {Neutronics Calculations for a Hypothetical Plasma-Jet-Driven Magneto-Inertial-Fusion Reactor},
author = {Rolison, Lucas Matthew and Fensin, Michael Lorne and Thio, Yong C. Francis and Hsu, Scott C. and Cruz, Edward Jeffrey},
abstractNote = {We present neutronics calculations for a hypothetical fusion reactor based on the repetitively pulsed concept of plasma-jet-driven magneto-inertial fusion (PJMIF). A PJMIF reactor is envisioned to have a replaceable, 3-m-radius spherical metal first wall exposed to 14.1-MeV neutrons, a fast-flowing FLiBe liquid blanket (with thickness 0.75 m) behind the first wall serving as the primary coolant and tritium-breeding medium, and finally an outer structural spherical wall shielded by the blanket. Cylindrical penetrations through both walls and the flowing blanket allow for hundreds of plasma-gun drivers to inject hypersonic plasma jets that form both the DT plasma target and high-Z spherically imploding plasma liner to compress the target. This research is the first to conduct Monte Carlo N Particle (MCNP6.2) and CINDER2008 neutronics calculations relevant to the PJMIF reactor configuration, with the primary objectives of (1) determining the neutron flux as a function of blanket thickness in the blanket and key reactor components and (2) the tritium production rate in the liquid blanket. These results will be used to estimate other quantities of interest, such as first-wall and gun-electrode lifetimes based on DPA accumulation, optimum blanket thickness, activation level of the outer wall and xenon liner, and achievable tritium-breeding ratios. Energy dependent flux tallies were used to calculate neutron flux inside the FLiBe blanket and outer wall, as well as the cylindrical ports where plasma guns are located. Tally multipliers of the flux in MCNP6.2 estimated tritium breeding ratio, DPA, and nuclear heating, while the depletion code CINDER2008 was used to compare tritium breeding ratios with MCNP6.2 and calculate activation of the outer wall and xenon liner. These calculations provide a baseline for blanket requirements necessary for power production in a PJMIF reactor.},
doi = {10.1080/15361055.2019.1613140},
journal = {Fusion Science and Technology},
number = 6,
volume = 75,
place = {United States},
year = {2019},
month = {5}
}

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