A methodology based on the linear reactivity model of core behavior has been developed and employed to evaluate fuel management tactics for improving uranium utilization in Pressurized Water Reactors in a once-through fuel cycle mode on a consistent basis. A major focus has been on the benefit of using burnable poison in conjunction with low-leakage fuel management schemes. Key features in the methodology, such as power weighting of batch reactivity values and correlation of neutron leakage effects with peripheral assembly power, were verified against results generated using detailed state-ofthe- art computer analyses. A relation between batch power fraction and batch reactivity was derived from a 1/2-group diffusion theory model, and simil...
Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission...
The purpose of this program is to demonstrate two techniques for improving fuel utilization in curre...
Originally presented as the first author's thesis, (Sc.D.) in the M.I.T. Dept. of Nuclear Engineerin...
Also presented as author's dissertation in substantially the same form. (Nuc. Eng., Ph. D., 1982)Inc...
Includes bibliographical referencesThis is the final summary progress report on a research program c...
Systematic procedures have been devised and applied to evaluate core design and fuel management stra...
Systematic procedures have been developed and applied to assess the uranium utilization potential of...
Includes bibliographical references (pages 315-318)Systematic procedures have been developed and app...
This is the final summary progress report on a research program' carried out within the MIT Energy L...
Low-leakage extended-burnup fuel management is a promising pressurized water reactor (PWR) improveme...
A new method has been developed to optimize pressurized water reactor core reload design for low-lea...
The production of long-lived transuranic (TRU) waste is a major disadvantage of fission-based nuclea...
In studying the position of the United States Department of Energy, Non-proliferation Alternative Sy...
Burnable poisons are used in all modern nuclear reactors to permit higher loading of fuel without th...
Burnable poisons play a critical role in long-life pressurized water reactors. Plate fuel elements h...
Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission...
The purpose of this program is to demonstrate two techniques for improving fuel utilization in curre...
Originally presented as the first author's thesis, (Sc.D.) in the M.I.T. Dept. of Nuclear Engineerin...
Also presented as author's dissertation in substantially the same form. (Nuc. Eng., Ph. D., 1982)Inc...
Includes bibliographical referencesThis is the final summary progress report on a research program c...
Systematic procedures have been devised and applied to evaluate core design and fuel management stra...
Systematic procedures have been developed and applied to assess the uranium utilization potential of...
Includes bibliographical references (pages 315-318)Systematic procedures have been developed and app...
This is the final summary progress report on a research program' carried out within the MIT Energy L...
Low-leakage extended-burnup fuel management is a promising pressurized water reactor (PWR) improveme...
A new method has been developed to optimize pressurized water reactor core reload design for low-lea...
The production of long-lived transuranic (TRU) waste is a major disadvantage of fission-based nuclea...
In studying the position of the United States Department of Energy, Non-proliferation Alternative Sy...
Burnable poisons are used in all modern nuclear reactors to permit higher loading of fuel without th...
Burnable poisons play a critical role in long-life pressurized water reactors. Plate fuel elements h...
Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission...
The purpose of this program is to demonstrate two techniques for improving fuel utilization in curre...
Originally presented as the first author's thesis, (Sc.D.) in the M.I.T. Dept. of Nuclear Engineerin...