The Methods and Applications of Monte Carlo in Low Energy (≲ 20 MeV) Neutron-Photon Transport (MORSE) Part II: Applications

  • T. A. Gabriel
Part of the Ettore Majorana International Science Series book series (EMISS, volume 3)


There are many problems of current interest in the area of radiation transport which involve the use of the neutron and gamma ray transport code MORSE.1 Some of these are:l) fusion reactor shielding2, 2) accelerator breeder design3 (electronuclear fuel production), 3) high energy nuclear instrumentation design4 (uranium calorimeters), and 4) accelerator beam stop activation.5 In the sections to follow,1) and 2) will be discussed. The reader is referred to Refs. 4 and 5 for a discussion of 3) and 4).


Track Length Detector Position Neutral Beam Injector Tritium Breeding Incident Proton Energy 
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Copyright information

© Plenum Press, New York 1980

Authors and Affiliations

  • T. A. Gabriel
    • 1
  1. 1.Oak Ridge National LaboratoryOak RidgeUSA

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