Multibatch fuel nanagement for gen IV fast reactors

Transactions of the American Nuclear Society

Volumn 97, Issue , 2007, Pages 404-405

  Driscoll, M J ^a   Handwerk, C S ^a  

^a Massachusetts Institute of Technology Cambridge   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BREEDING RATIOS; BURN-UP; ECONOMIC INCENTIVES; FABRICATION TECHNOLOGIES; FUEL BATCHES; FUEL COSTS; FUEL MANAGEMENTS; PLANT CAPACITY FACTORS; RESIDENCE TIMES; SPECIFIC POWERS;

FAST REACTORS; FUELS; NUCLEAR FUELS; NUCLEAR REACTORS;

NUCLEAR FUEL REPROCESSING;

EID: 55349146917     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. M.J. DRISCOLL, T.J. DOWNAR, E.E. PILAT, The Linear Reactivity Model for Nuclear Fuel Management, American Nuclear Society (1990).
2. 2-Cooled Fast Reactor," MIT-ANP-TR-113, May (2007).
3. S.G. HONG, Y.I. KIM, "Comparison of the ENDF/B-VI and JEF2.2 Nuclear Data for the ENHS Benchmark Problem," Trans. Am. Nucl. Soc., 85, 111 (2001).
4. K. SHIRATA, T. SANDA, F. NAKASHIMA, "Spatial Neutronic Decoupling of Large Fast Breeder Cores: Application to Nuclear Core Design Method," Nucl. Sci. Eng., 131, 187 (1999).