ML19221B657: Difference between revisions

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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

Enclosure 2: Safety Evaluation Report (Letter to B. Seawright Certificate of Compliance No. 9378, Revision No. 0, for the Model No. HI-STAR 100MB Package)
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