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Title: Neutron Capture Cross Section Measurements at n{sub T}OF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste

Abstract

Accurate and reliable neutron capture cross section data for actinides are necessary for the proper design, safety regulation and precise performance assessment of transmutation devices such as Fast Critical Reactors or Accelerator Driven Systems. In particular, the neutron capture cross sections of 237Np, 240Pu and 243Am play a key role in the design and optimization of strategies for the Transmutation of Nuclear Waste. The listed cross sections have been measured in 2004 at n{sub T}OF with a high accuracy due to a combination of features unique in the world: high instantaneous neutron fluence and excellent energy resolution of the n{sub T}OF facility, innovative Data Acquisition System based on flash ADCs and the use of a high performance BaF2 Total Absorption Calorimeter as a detection device.

Authors:
; ; ; ; ; ; ;  [1]; ; ; ;  [2]; ; ; ; ; ; ; ;  [3]
  1. Centro de Investigaciones Energeticas Medioambientales y Technologicas, Madrid (Spain)
  2. Istituto Nazionale di Fisica Nucleare, Trieste (Italy)
  3. CEA/Saclay - DSM, Gif-sur-Yvette (France)
Publication Date:
OSTI Identifier:
20798309
Resource Type:
Journal Article
Journal Name:
AIP Conference Proceedings
Additional Journal Information:
Journal Volume: 819; Journal Issue: 1; Conference: 12. international symposium on capture gamma-ray spectroscopy and related topics, Notre Dame, IN (United States), 4-9 Sep 2005; Other Information: DOI: 10.1063/1.2187878; (c) 2006 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0094-243X
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; AMERICIUM 243; CAPTURE; CROSS SECTIONS; DATA ACQUISITION SYSTEMS; ENERGY RESOLUTION; NEPTUNIUM 237; NEUTRON FLUENCE; NEUTRON REACTIONS; NEUTRONS; OPTIMIZATION; PLUTONIUM 240; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTES; SAFETY; TIME-OF-FLIGHT METHOD; TRANSMUTATION

Citation Formats

Cano-Ott, D, Alvarez-Velarde, F, Embid-Segura, M, Gonzalez-Romero, E, Guerrero, C, Martinez, T, Villamarin, D, Vincente, M C, Abbondanno, U, Fujii, K, Milazzo, P M, Moreau, C, Aerts, G, Andriamonje, S, Berthoumieux, E, Dridi, W, Gunsing, F, Pancin, J, Perrot, L, and Plukis, A. Neutron Capture Cross Section Measurements at n{sub T}OF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste. United States: N. p., 2006. Web. doi:10.1063/1.2187878.
Cano-Ott, D, Alvarez-Velarde, F, Embid-Segura, M, Gonzalez-Romero, E, Guerrero, C, Martinez, T, Villamarin, D, Vincente, M C, Abbondanno, U, Fujii, K, Milazzo, P M, Moreau, C, Aerts, G, Andriamonje, S, Berthoumieux, E, Dridi, W, Gunsing, F, Pancin, J, Perrot, L, & Plukis, A. Neutron Capture Cross Section Measurements at n{sub T}OF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste. United States. https://doi.org/10.1063/1.2187878
Cano-Ott, D, Alvarez-Velarde, F, Embid-Segura, M, Gonzalez-Romero, E, Guerrero, C, Martinez, T, Villamarin, D, Vincente, M C, Abbondanno, U, Fujii, K, Milazzo, P M, Moreau, C, Aerts, G, Andriamonje, S, Berthoumieux, E, Dridi, W, Gunsing, F, Pancin, J, Perrot, L, and Plukis, A. 2006. "Neutron Capture Cross Section Measurements at n{sub T}OF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste". United States. https://doi.org/10.1063/1.2187878.
@article{osti_20798309,
title = {Neutron Capture Cross Section Measurements at n{sub T}OF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste},
author = {Cano-Ott, D and Alvarez-Velarde, F and Embid-Segura, M and Gonzalez-Romero, E and Guerrero, C and Martinez, T and Villamarin, D and Vincente, M C and Abbondanno, U and Fujii, K and Milazzo, P M and Moreau, C and Aerts, G and Andriamonje, S and Berthoumieux, E and Dridi, W and Gunsing, F and Pancin, J and Perrot, L and Plukis, A},
abstractNote = {Accurate and reliable neutron capture cross section data for actinides are necessary for the proper design, safety regulation and precise performance assessment of transmutation devices such as Fast Critical Reactors or Accelerator Driven Systems. In particular, the neutron capture cross sections of 237Np, 240Pu and 243Am play a key role in the design and optimization of strategies for the Transmutation of Nuclear Waste. The listed cross sections have been measured in 2004 at n{sub T}OF with a high accuracy due to a combination of features unique in the world: high instantaneous neutron fluence and excellent energy resolution of the n{sub T}OF facility, innovative Data Acquisition System based on flash ADCs and the use of a high performance BaF2 Total Absorption Calorimeter as a detection device.},
doi = {10.1063/1.2187878},
url = {https://www.osti.gov/biblio/20798309}, journal = {AIP Conference Proceedings},
issn = {0094-243X},
number = 1,
volume = 819,
place = {United States},
year = {Mon Mar 13 00:00:00 EST 2006},
month = {Mon Mar 13 00:00:00 EST 2006}
}