Loft fuel modules design, characterization, and fabrication program

Russell, M.L.

doi:10.2172/4134856

Cited by 2 publications

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“…The LOFT reactor (Loss -of-fluid -test) located at the Idaho National Engineering Laboratory, Idaho Falls, Idaho is an experimental reactor whose purpose is to: (1) Evaluate the capability of analytical methods that predict the loss-of-coolantaccident (LOCA) responses for large pressurized -water power reactors, the performance of engineered safety systems, and the margins of safety in the safety systems performance. (2) Identify any unexpected events or thresholds not presently accounted for in the analysis of reactor response or in the design of engineered safety systems.1…”

Section: Introductionmentioning

confidence: 99%

“…30 / SP/E Vol. 247 Advances in Laser Engineering and Applications (1980) Introduction The LOFT reactor (Loss-of-fluid-test) located at the Idaho National Engineering Laboratory, Idaho Falls, Idaho is an experimental reactor whose purpose Is to: (1) Evaluate the capability of analytical methods that predict the loss-of-coolantaccident (LOCA) responses for large pressurized-water power reactors, the performance of engineered safety systems, and the margins of safety in the safety systems performance.…”

Section: Introductionmentioning

confidence: 99%

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<title>External Attachment of Titanium Sheathed Thermocouples to Zirconium Nuclear Fuel Rods For The Loss-Of-Fluid-Test (LOFT) Reactor</title>

Welty

1980

Advances in Laser Engineering and Applications

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The Exxon Nuclear Company, Inc. acting as a Subcontractor to EG &G Idaho Inc., Idaho National Engineering Laboratory, Idaho Falls, Idaho, has developed a welding process to attach titanium sheathed thermocouples to the outside of the zircaloy clad fuel rods.The fuel rods and thermocouples are used to test simulated loss -of-coolant-accident (LOCA) conditions in a pressurized water reactor (LOFT Reactor, Idaho National Laboratory).The design goals were to (1) reliably attach thermocouples to the zircaloy fuel rods, (2) achieve or exceed a life expectancy of 6,000 hours of reactor operation in a borated water environment of 316 °C at 2240 psi, (3) provide and sustain repeatable physical and metallurgical properties in the instrumented rods subjected to transient temperatures up to 1538 °C with blowdown, shock, loading, and fast quench.A laser beam was selected as the optimum welding process because of the extremely high energy input per unit volume that can be achieved allowing local fusion of a small area irrespective of the difference in material thickness to be joined.A commercial pulsed laser and energy control system was installed along with specialized welding fixtures.Laser room facility requirements and tolerances were established. Performance qualifications and detailed welding procedures were also developed. Product performance tests were conducted to assure that engineering design requirements could be met on a production basis.Irradiation tests showed no degradation of thermocouples or weld structure. Fast thermal cycle and heater rod blowdown reflood tests were made to subject the weldments to high temperatures, high pressure steam, and fast water quench cycles.From the behavior of these tests, it was concluded that the attachment welds would survive a series of reactor safety tests.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

<title>External Attachment of Titanium Sheathed Thermocouples to Zirconium Nuclear Fuel Rods For The Loss-Of-Fluid-Test (LOFT) Reactor</title>

Welty

1980

Advances in Laser Engineering and Applications

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show abstract

“…The LOFT reactor (Loss -of-fluid -test) located at the Idaho National Engineering Laboratory, Idaho Falls, Idaho is an experimental reactor whose purpose is to: 1) Evaluate the capability of analytical methods that predict the loss-of-coolant -accident (LOCA) responses of large pressurized water power reactors, the performance of engineered safety systems, and the margins of safety in the safety systems performance. 2) Identify any unexpected events or thresholds not presently accounted for in the analysis of reactor response or in the design of engineered safety systems.…”

Section: Introductionmentioning

confidence: 99%

<title>Internal Attachment Of Laser Beam Welded Stainless Steel Sheathed Thermocouples Into Stainless Steel Upper End Caps In Nuclear Fuel Rods For The Loss-Of-Fluid-Test (LOFT) Reactor</title>

Welty

Reid

1980

Advances in Laser Engineering and Applications

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The Exxon Nuclear Company, Inc., acting as a subcontractor to EG &G Idaho Inc., Idaho National Engineering Laboratory, Idaho Falls, Idaho, conducted a laser beam welding study to attach internal stainless steel thermocouples into stainless steel upper end caps in nuclear fuel rods.The fuel rods and thermocouples are used to test simulated loss -of-coolant -accident (LOCA) conditions in a pressurized water reactor (LOFT reactor, Idaho National Laboratory).The objective of this study was to determine the feasibility of laser welding a single 0.063 inch diameter stainless steel (304) sheathed thermocouple into a stainless steel (316) upper end cap for nuclear fuel rods.A laser beam was selected because of the extremely high energy input in unit volume that can be achieved allowing local fusion of a small area irrespective of the difference in material thickness to be joined.A special weld fixture was designed and fabricated to hold the end cap and the thermocouple with angular and rotational adjustment under the laser beam.A commercial pulsed laser and energy control system was used to make the welds.Process tests were performed and evaluated. Results indicated that successful welds could be made using the laser system.A process qualification was written specifying laser energy, spot size and weld overlay.This program was successfully concluded by welding seventeen (17) centerline fuel rodsfor the LOFT reactor.

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Loft fuel modules design, characterization, and fabrication program

Abstract: H.A. Rau managed the design, development, and fabrication program for the instrumentation penetration assemblies and the fabrication program for the fuel module assembly. C. E. Forkel managed the fabrication program for the upp_er support structures.

Cited by 2 publications

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<title>External Attachment of Titanium Sheathed Thermocouples to Zirconium Nuclear Fuel Rods For The Loss-Of-Fluid-Test (LOFT) Reactor</title>

<title>External Attachment of Titanium Sheathed Thermocouples to Zirconium Nuclear Fuel Rods For The Loss-Of-Fluid-Test (LOFT) Reactor</title>

<title>Internal Attachment Of Laser Beam Welded Stainless Steel Sheathed Thermocouples Into Stainless Steel Upper End Caps In Nuclear Fuel Rods For The Loss-Of-Fluid-Test (LOFT) Reactor</title>

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