Investigation of the infinite medium integral neutronic data for incident fusion source neutrons |
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| Affiliation: | 1. Centre d’Etudes Nucléaires de Bordeaux Gradignan, Le Haut-Vigneau, BP 120, 33175 Gradignan Cedex, France;2. Chimie Nucléaire Analytique et Bioenvironnementale, Le Haut-Vigneau, BP 120, 33175 Gradignan Cedex, France;3. Laboratoire de Sciences de la Terre, Ecole Normale Supérieure de Lyon, 46 Allée d’Italie, 69007 Lyon, France;4. Research School of Physical Sciences and Engineering, The Australian National University, Canberra, ACT 0200, Australia;5. Laboratoire d’Ecophysiologie et d’Ecotoxicologie des Systèmes Aquatiques, Station marine d’Arcachon, Place du Dr Peyneau, 33120 Arcachon, France;6. Laboratoire des Composites Thermostructuraux, CNRS-Snecma-CEA-UB1, 33405 Talence Cedex, France;1. Área de Ingeniería en Recursos Energéticos, Universidad Autónoma Metropolitana-Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, México DF., CP 09340, Mexico;2. Retorno Québec 6, Col. Burgos de Cuernavaca 62580, Temixco, Mor., Mexico;2. Department of Urology, Stanford University School of Medicine, Stanford, California;3. Department of Urology, Santa Clara Valley Medical Center, San Jose, California;4. Department of Urology, Palo Alto VA Hospital, Palo Alto, California;5. Department of Surgery, Urological Research Centre, University of Western Australia, Perth, Western Australia, Australia |
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| Abstract: | In the present work, the physical behavior of integral data in infinite medium has been evaluated for incident fusion neutrons with the help to the 3-D Monte Carlo code. In a fusion reactor blanket with finite dimension, the integral quantities will be more or less different from the infinitive medium results, depending on the neutron leakage fraction. Design studies foresee the reduction of the neutron leakage out of the blanket as possible in order to prevent the nuclear heating in super conducting fusion magnets and to keep all neutrons primarily in the coolant. The most important materials in fusion technology, namely tritium, beryllium, lead, thorium, and uranium have been investigated in infinitive medium. The main purpose of this work is to calculate the integral tritium breeding ratio, 233U breeding rate, 239Pu breeding rate, heat release, neutron multiplication ratio through (n,x) and fission (when applicable) reactions in those mixtures which are composed when first UO2 and ThO2 are mixed with natural lithium (Nat.Li) or 6Li for a volume fraction from 0 to 100%. Then the variable UO2-Nat.Li (UO2 mixed with Nat.Li) and UO2-6Li (UO2 mixed with 6Li) compositions will be mixed with Beryllium (Be) and Lead (Pb) for a volume fraction from 0 to 100%. However, the variable TO2-Nat.Li (ThO2 mixed with Nat.Li) and ThO2-6Li (ThO2 mixed with 6Li) compositions will be mixed with Be and Pb for a volume fraction mentioned above. |
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