10-242-UCF3-022
Low Fluence Behavior of Metallic Fuels
- Program
- NSUF
- Project
- Low Fluence Behavior of Metallic Fuels
- Reactor
- ATR
- Reactor Position
- B-8
- Sample Id Code
- 10-242-UCF3-022
- Capsule
- UCF-17
- Packet
- No Packet Defined
- Material Code
- BZ
- Material Name
- Zr
- Material Description
- Disc
- KGT Num
- 3406
- Specimen Type
- TEM
- Dimensions (mm)
- 3
- Number Of Samples
- 1
- Samples Remaining
- 1
- Date Added
- No Date Added Defined
- Available for Research
-
Yes
- Anticipated Availability
- October 1, 2019
- Storage Facility
- Hot Fuel Examination Facility
- Notes
- The radionuclide source terms for the UCF-3 experiment components and capsules were evaluated using the maximum MCNP-calculated neutron flux in any experiment component and scaled to the N source power 20.3 MW. This yielded a neutron flux of 7.39E+14 neutrons/cm2-sec. With the addition of the historical 8.5% instrumentation uncertainty and the effect of all four OSCC banks rotated to 155° (1.20 multiplier), the flux increases to 9.63E+14.
- Planned Temp (°C)
- 600.00
- Planned Dose (DPA)
- 1
- Planned Fluence (n/cm²)
- No planned Fluence Value Defined
- Planned Flux (n/cm²/s)
- No planned Flux Value Defined
- Planned Environment
- 75% He, 25% Ar
- As Run Temp (°C)
- No As Run Temp Defined
- As Run Dose (DPA)
- No as Run Dose Value Defined
- As Run Total Dose (DPA)
- 2.25
- As Run Fluence (n/cm²)
- No as Run Fluence Value Defined
- As Run Total Fluence (n/cm²)
- No as Run Total Fluence Value Defined
- As Run Flux (n/cm²/s)
- 9.63E+14
- As Run Environment
- No As Run Environment Defined
