ML19221B657: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 19: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:**** | ||
Classification Mechanical Properties Peak Cladding Temperatures Cover Gas | |||
Journal of Metals | |||
Governing Regionalization Configuration | |||
Component Specifications | |||
Overview of the Thermal Model | |||
Description of HI-STAR 100MB 3D Thermal Model | |||
Time-to-Boil Limits | |||
Cold | |||
Maximum Normal Operating Pressure | |||
Thermal Evaluation under Normal Conditions of Transport | |||
Fuel Rods | |||
Design Basis Fire Event | |||
Structural Design | |||
License Drawings | |||
Containment Criteria | |||
Containment Criteria | |||
Leakage Integrity Tests for the HI-STAR 100MB Overpack | |||
* | |||
***** | |||
"In lieu of an explicit benchmarking analysis, the applicant may use the bias (i) and bias uncertainty (k i) values estimated in NUREG/CR-7108 using the Monte Carlo uncertainty sampling method, as shown in Tables 3 and 4 below. These values may be used directly, provided that: | |||
*the applicant uses the same depletion code and cross section library as was used in NUREG/CR-7108 (SCALE/TRITON and the ENDF/B-V or -VII cross section library), *the applicant can justify that its design is similar to the hypothetical GBC-32 system design used as the basis for the NUREG/CR-7108 isotopic depletion validation, and credit is limited to the specific nuclides listed in Tables 1 and 2, *demonstrates that the credited minor actinide and fission product worth is no greater than 0.1 in k eff." | |||
*"With respect to reactivity (calculated keff), the MPC-32M with design basis neutron absorber shows the lowest value, as expected. However, even when adjusted to the areal density value of the GBC-32, the reactivity is lower. This is because the neutron absorber is an integral part of the basket structure for the MPC-32M and therefore surrounds each assembly, while for the GBC-32 the neutron absorber is present in sheets and does not cover the corners of the cells. Again, it needs to be seen if these differences affect the more detailed neutronic behavior analyzed in the form of the neutron spectra and reaction rates. | |||
*As expected, the EALF values follow this inversely, i.e. the higher reactivity basket has the lower EALF for the same fuel type and fuel composition. | |||
*There are no significant differences between the different fuel compositions analyzed." | |||
," Nucl. Technol. | |||
Removal of Contents from Bare Basket CaskPreparation for Transport, | |||
Loading the MPC with Spent Fuel | |||
Loading the Bare Basket Cask with Spent Fuel, Package Unloading,Removal of Contents from MPC , Removal of Contents from Bare Basket Cask | |||
Thermal TestPost-Shipment HBF Integrity Acceptance Test}} |
Revision as of 23:55, 12 September 2019
ML19221B657 | |
Person / Time | |
---|---|
Site: | 07109378 |
Issue date: | 08/09/2019 |
From: | John Mckirgan Spent Fuel Licensing Branch |
To: | Seawright B Holtec |
Saverot P | |
Shared Package | |
ML19221B654 | List: |
References | |
EPID L-2018-NEW-0000 | |
Download: ML19221B657 (68) | |
Text
Classification Mechanical Properties Peak Cladding Temperatures Cover Gas
Journal of Metals
Governing Regionalization Configuration
Component Specifications
Overview of the Thermal Model
Description of HI-STAR 100MB 3D Thermal Model
Time-to-Boil Limits
Cold
Maximum Normal Operating Pressure
Thermal Evaluation under Normal Conditions of Transport
Fuel Rods
Design Basis Fire Event
Structural Design
License Drawings
Containment Criteria
Containment Criteria
Leakage Integrity Tests for the HI-STAR 100MB Overpack
"In lieu of an explicit benchmarking analysis, the applicant may use the bias (i) and bias uncertainty (k i) values estimated in NUREG/CR-7108 using the Monte Carlo uncertainty sampling method, as shown in Tables 3 and 4 below. These values may be used directly, provided that:
- the applicant uses the same depletion code and cross section library as was used in NUREG/CR-7108 (SCALE/TRITON and the ENDF/B-V or -VII cross section library), *the applicant can justify that its design is similar to the hypothetical GBC-32 system design used as the basis for the NUREG/CR-7108 isotopic depletion validation, and credit is limited to the specific nuclides listed in Tables 1 and 2, *demonstrates that the credited minor actinide and fission product worth is no greater than 0.1 in k eff."
- "With respect to reactivity (calculated keff), the MPC-32M with design basis neutron absorber shows the lowest value, as expected. However, even when adjusted to the areal density value of the GBC-32, the reactivity is lower. This is because the neutron absorber is an integral part of the basket structure for the MPC-32M and therefore surrounds each assembly, while for the GBC-32 the neutron absorber is present in sheets and does not cover the corners of the cells. Again, it needs to be seen if these differences affect the more detailed neutronic behavior analyzed in the form of the neutron spectra and reaction rates.
- As expected, the EALF values follow this inversely, i.e. the higher reactivity basket has the lower EALF for the same fuel type and fuel composition.
- There are no significant differences between the different fuel compositions analyzed."
," Nucl. Technol.
Removal of Contents from Bare Basket CaskPreparation for Transport,
Loading the MPC with Spent Fuel
Loading the Bare Basket Cask with Spent Fuel, Package Unloading,Removal of Contents from MPC , Removal of Contents from Bare Basket Cask
Thermal TestPost-Shipment HBF Integrity Acceptance Test