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Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning, Fission-Fusion Hybrid Reactor Design

Journal Article · · Nuclear Science and Engineering
 [1];  [2];  [2];  [2];  [2];  [2]
  1. University of Wisconsin–Madison, Department of Engineering Physics, 1500 Engineering Drive, Madison, Wisconsin 53711; OSTI
  2. University of Wisconsin–Madison, Department of Engineering Physics, 1500 Engineering Drive, Madison, Wisconsin 53711
Not provided.
Research Organization:
Univ. of Wisconsin, Madison, WI (United States)
Sponsoring Organization:
USDOE Advanced Research Projects Agency - Energy (ARPA-E)
DOE Contract Number:
AR0001258
OSTI ID:
2422350
Journal Information:
Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 8 Vol. 197; ISSN 0029-5639
Publisher:
Taylor & Francis
Country of Publication:
United States
Language:
English

References (19)

The Need for Integrating the Back End of the Nuclear Fuel Cycle in the United States of America journal January 2018
Informing Nuclear Energy Systems with Proliferation Risk journal July 2012
The core design of ALFRED, a demonstrator for the European lead-cooled reactors journal October 2014
Separations and Transmutation Criteria to Improve Utilization of a Geologic Repository journal April 2006
Tritium supply and use: a key issue for the development of nuclear fusion energy journal November 2018
Literature review of lead-lithium thermophysical properties journal January 2019
Long-term storage of spent nuclear fuel journal February 2015
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data journal December 2011
Acceleration techniques for the direct use of CAD-based geometry in fusion neutronics analysis journal December 2010
The Integral Fast Reactor Concept: Physics of Operation and Safety journal December 1988
The fusion hybrid journal May 1979
The Paramak: automated parametric geometry construction for fusion reactor designs. journal January 2021
Solving the Spent Nuclear Fuel Problem by Fissioning Transuranics in Subcritical Advanced Burner Reactors Driven by Tokamak Fusion Neutron Sources journal August 2017
Depletion capabilities in the OpenMC Monte Carlo particle transport code journal March 2021
Material compatibility with isothermal Pb–Li journal June 2012
Fusion by beam ions in a low collisionality, high mirror ratio magnetic mirror journal November 2022
Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400) journal May 2022
Compatibility of materials in fusion first wall and blanket structures cooled by liquid metals journal September 1992
Neutronic Model of a Mirror Based Fusion-Fission Hybrid for the Incineration of Spent Nuclear Fuel and with Potential for Power Generation journal January 2011

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