152
Views
5
CrossRef citations to date
0
Altmetric
Applications to Accelerator Technology including Accelerator-Driven Systems

Comparative Analysis of ENDF, JEF and JENDL Data Libraries by Modelling High Temperature Reactors and Plutonium Based Fuel Cycles

, , , , , , & show all
Pages 1167-1170 | Published online: 27 Aug 2014

References

  • General Atomics, “Gas Turbine-Modular Helium Reactor (GT- MHR) Conceptual Design Description Report”, report 910720, GA project No. 7658, San Diego, USA (1996).
  • H.R. Trellue and D.I. Poston, “User’s Manual, Version 2.0 for Montebums, Version 5B”, LANL preprint LA-UR-99-4999 (1999).
  • ENDF/B-VI, “The US Evaluated Neutron Nuclear Data Library for Neutron Reactions”, IAEA-Vienna, IAEA-NDS-100, Rev. 6 (1995) .
  • JENDL-3.2, “The Japanese Evaluated Nuclear Data Library”, IAEA-Vienna, IAEA-NDS-110, Rev. 5 (1994).
  • JEF-2.2, “The Evaluated Neutron Nuclear Data Library of the NEA Data Bank”, IAEA-Vienna, IAEA-NDS-120, Rev. 3 (1996) .
  • C. Rodriguez et at, “The Once-through Helium Cycle for Economical Transmutation in Secure, Clean and Safe Manner”, paper 73 in the Proc. of the 6th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 11-13 Dec. 2000, Madrid, Spain.
  • D. Ridikas et al., “Critical and Sub-Critical GT-MHRs for Waste Disposal and Proliferation-Resistant Fuel Cycles”, paper 71 in the same Proc. as Ref.6)
  • J.M. Kendall, “IAEA High Temperature Gas Cooled Reactor Activities”, International Atomic Energy Agency (IAEA), Sep. 2000; http://www.iaea.org/inis/aws/htgr/; Xavier Raepsaet (private communication).
  • G. Fioni et al., “The Mini-Inca Project: Experimental Study of the Transmutation of Actinides in High Intensity Neutron Fluxes”, see paper #338 of this conference.
  • J.F. Briesmeister, “MCNP - A General Monte Carlo N-Particle Code, ” Technical Report LA-12625-M, LANL (1997).
  • RSIC Computer Code Collection, “ORIGEN 2.1 - Isotope Generation and Depletion Code Matrix Exponential Method”, RSIC report CCC-371 (1991).
  • Nuclear Energy Agency, NEA Data Bank in Paris, France; http:// w w w. nea. fr/html /databank/.
  • L. Bletzacker, “Influence des Bibliothèques de Sections Effi- caces ENDF, JEF et JENDL sur les Performances du Réacteur à Haute Température GT-MHR”, MSc thesis in preparation (2001).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.