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Ganley, J.T.; West, G.B.; Whittemore, W.L.
Proceedings of the third Asian symposium on research reactor1992
Proceedings of the third Asian symposium on research reactor1992
AbstractAbstract
[en] The 65 TRIGA reactors and reactors refueled with TRIGA fuel have had a wide range of power levels (10 kW to 14 MW). Many of the higher power reactors (P ≥ 1 MW) have benefitted from use of long lived TRIGA LEU fuel. All the well recognized TRIGA safety features are retained. For improved reactor performance the standard square fuel cluster can be redesigned to provide a hexagonal array with improved utilization of cooling water. The result can be higher power densities and hence higher neutron fluxes for the same reactor power. TRIGA research reactors with 5 to 10 MW power levels and higher power densities can provide in-core thermal neutron fluxes in excess of 3 x 1014 n/cm2.s and reflector neutron fluxes available for beamports in excess of 1014 n/cm2.s. (author)
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Japan Atomic Energy Research Inst., Tokyo (Japan); 694 p; Mar 1992; p. 136-141; 3. Asian symposium on research reactor; Hitachi, Ibaraki (Japan); 11-14 Nov 1991
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