San Jose, CA, United States of America

Bart Alan Smith


Average Co-Inventor Count = 2.7

ph-index = 4

Forward Citations = 36(Granted Patents)


Company Filing History:


Years Active: 1976-1978

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4 patents (USPTO):Explore Patents

Title: Bart Alan Smith: Innovator in Nuclear Fuel Technology

Introduction

Bart Alan Smith is a notable inventor based in San Jose, California. He has made significant contributions to the field of nuclear fuel technology, holding a total of four patents. His work focuses on improving the efficiency and safety of nuclear fuel assemblies.

Latest Patents

Among his latest patents is the "Nuclear fuel element spacer means." This invention provides a spacer retaining element designed to maintain proper axial spacing between individual spacers in a nuclear fuel assembly. The innovative lug-slot arrangement prevents the rod from rotating and ensures that the spacer cannot be inserted upside down. Another significant patent is the "Channel follower leakage restrictor," which offers an improved method to control coolant leakage between the flow channel and the lower tie plate of a nuclear fuel assembly. This invention utilizes a movable element that compensates for any movement of the flow channel, effectively controlling coolant flow and enhancing the overall safety of the assembly.

Career Highlights

Bart Alan Smith is currently employed at General Electric Company, where he continues to develop innovative solutions in nuclear technology. His expertise and dedication to his work have positioned him as a key figure in his field.

Collaborations

Throughout his career, Smith has collaborated with notable colleagues, including Kenneth Wood Brayman and Louis Amaral. These partnerships have contributed to the advancement of nuclear fuel technology and the successful development of his patents.

Conclusion

Bart Alan Smith's contributions to nuclear fuel technology through his patents demonstrate his commitment to innovation and safety in the industry. His work continues to influence the field and improve the efficiency of nuclear fuel assemblies.

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