1995
DOI: 10.1016/0370-2693(95)00154-d
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Experimental determination of the energy generated in nuclear cascades by a high energy beam

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Cited by 114 publications
(31 citation statements)
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“…A first experiment (FEAT) [1] was performed to test the concept of energy gain in the Energy Amplifier (EA) system proposed by C. Rubbia [2], a system designed to destroy all actinide elements by fission. As a consequence, the EA is also producing energy while it is destroying the TRansUranium (TRU) content of nuclear reactor waste.…”
Section: Introductionmentioning
confidence: 99%
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“…A first experiment (FEAT) [1] was performed to test the concept of energy gain in the Energy Amplifier (EA) system proposed by C. Rubbia [2], a system designed to destroy all actinide elements by fission. As a consequence, the EA is also producing energy while it is destroying the TRansUranium (TRU) content of nuclear reactor waste.…”
Section: Introductionmentioning
confidence: 99%
“…In a system such as the EA, where TRUs are destroyed by fission, long-term (≥ 500 years 1 ) radiotoxicity of the waste is dominated by long-lived fission fragments (LLFFs) which can, in practice, only be destroyed by nuclear decay following neutron capture.…”
Section: Introductionmentioning
confidence: 99%
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“…However, studies have shown that the number of generated neutrons normalized to the beam power saturates as the proton energy exceeds 1 GeV [11]. In addition, as shown in Figure 2, the Monte Carlo simulations show that the 1 GeV proton stops after travelling ~62 cm into the LBE target and deposits 99.8% of its energy.…”
Section: Spallation Neutron Source Designmentioning
confidence: 93%
“…Therefore, the neutron destruction and production operator can be calculated as (11) In the Eq. 11, the microscopic reaction rates are approximated with the reaction rates calculated by MCB5 fixed-source problem, and the multiplication factors k 0 and k 1 # 39alamo39g39 the reaction rates at the end of the burnup step fr=open('mass_total','r') # macroscopic chifission reaction rates sum_1_fis=0.0 # macroscopic capture reaction rates for non-gas-FPs, gas FPs sum_1_cap_FPs=0.0 sum_1_cap_Fpgas=0.0 # calculate the fission reaction rates after burnup for line in fr: print 'actinides no adjustment:',x sum_atom_den = sum_atom_den + dentmp …”
Section: Appendix A: Discrete Feeding Factor Estimatementioning
confidence: 99%