ML19169A077

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Letter to P. Noss Authorization for Shipment of the Model No. Brr Package with Test Fuel Segments (W/Enclosure)
ML19169A077
Person / Time
Site: 07109341
Issue date: 06/14/2019
From: John Mckirgan
Spent Fuel Licensing Branch
To: Noss P
Orano Federal Services
Santos N
References
EPID L-2018-LLA-0117
Download: ML19169A077 (22)


Text

Code of Federal Regulations

Total fissile mass Total non-fissile mass Initial enrichment of uranium-235 (235U) Mass of 235 U Mass of plutonium-239 (239 Pu) Mass of plutonium-241 (241 Pu) Maximum weight of the payload Burnup Fuel rod length Total length of segments Fuel mass per rod Decay heat generation

1.1Packaging .....................................................................................................................

.... 11.2Contents ......................................................................................................................

...... 22.1Description of Structural Design .................................................................................... 32.2Evaluation of the Structural Design ............................................................................... 42.3Evaluation Findings ......................................................................................................... 53.1Description of the Thermal Design ................................................................................. 63.2Evaluation of the Thermal Design .................................................................................. 63.3Evaluation Findings ......................................................................................................... 65.1Description of Shielding Design ..................................................................................... 75.2Radiation Source Specification ...................................................................................... 75.3Shielding Model ................................................................................................................ 95.4Shielding Evaluation ...................................................................................................... 105.5Evaluation findings ........................................................................................................ 11

Code of Federal Regulations

1.1 Packaging

1.2 Contents

Total fissile mass Total non-fissile mass Initial enrichment of uranium-235 (235 U) Mass of 235 U Mass of plutonium-239 (23 9 Pu) Mass of plutonium-241 (241 Pu) Payload Burnup Fuel rod length Total length of segments Maximum diameter for fuel rod (including cladding) Fuel mass per rod Decay heat generation 2.1 Description of Structural Design 2.2 Evaluation of the Structural Design

2.3 Evaluation Findings

3.1 Description of the Thermal Design 3.2 Evaluation of the Thermal Design

3.3 Evaluation Findings

5.1 Description of Shielding Design

5.2 Radiation Source Specification

5.3 Shielding Model

5.4 Shielding Evaluation

5.5 Evaluation findings

Total fissile mass Total non-fissile mass Initial enrichment of 235 U Mass of 235 U Mass of 23 9 Pu Mass of 241 Pu Payload Burnup Fuel rod length Total length of segments Maximum diameter for fuel rod (including cladding) Fuel mass per rod Decay heat generation