Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base
- 1 March 1986
- journal article
- research article
- Published by Taylor & Francis in Fusion Technology
- Vol. 9 (2) , 286-307
- https://doi.org/10.13182/fst86-a24716
Abstract
Estimates of the uncertainty ΔD in predicting the achievable tritium breeding ratio (TBR) due to the uncertainties in nuclear data base are presented for several fusion blanket concepts. Specifically, the impact of the current uncertainties in measuring basic nuclear data on the calculated TBR is analyzed and discussed for four leading blanket designs that utilize different breeding materials, namely, Li2O, 17Li-83Pb, LiAlO2, and Flibe. The impact on the TBR values of various evaluations for beryllium, which is employed as a multiplier in the latter two blankets, has been studied. Estimates for ΔD in other blanket concepts have also been assessed. Moreover, estimates have been made, based on previous studies, for the contribution to ΔD introduced by using neutron cross-section libraries that have different group structure and weighting spectra.Based on statistically incorporating the present cross-section uncertainties and their correlation in the analysis, the range of the uncertainty in TBR was ...Keywords
This publication has 18 references indexed in Scilit:
- Deuterium-Tritium Fuel Self-Sufficiency in Fusion ReactorsFusion Technology, 1986
- Tritium Breeding Benchmark Calculations for a Li17Pb83Blanket with Steel StructureFusion Technology, 1984
- Comparison of one- and two-dimensional cross-section sensitivity calculations for a fusion reactor shielding experimentPublished by Office of Scientific and Technical Information (OSTI) ,1979
- Macroscopic cross section sensitivity study for fusion reactor shielding experimentsPublished by Office of Scientific and Technical Information (OSTI) ,1978
- Double-Differential Beryllium Neutron Cross Sections at Incident Neutron Energies of 5.9, 10.1, and 14.2 MeVNuclear Science and Engineering, 1977
- Uncertainties in Calculated Heating and Radiation Damage in the Toroidal Field Coil of a Tokamak Experimental Power Reactor Due to Neutron Cross-Section ErrorsNuclear Technology, 1977
- Application of FORSS sensitivity and uncertainty methodology to fast reactor benchmark analysisPublished by Office of Scientific and Technical Information (OSTI) ,1976
- Comparison of the Cross-Section Sensitivity of the Tritium Breeding Ratio in Various Fusion-Reactor BlanketsNuclear Science and Engineering, 1975
- Cross-Section Sensitivity of Breeding Ratio in a Fusion-Reactor BlanketNuclear Science and Engineering, 1974
- Sensitivity of Secondary Gamma-Ray Dose to Angular Distribution of Gamma Rays from Neutron Inelastic ScatteringNuclear Science and Engineering, 1970