|
Products
Charpy/Impact
Testing
Drop
Tower
Pendulum Machines
Automatic Charpy
Machines
Instrumented
Impact Testing
Quality Control
Specimens
Double Pendulum
Dynamic Tear
In-Situ Heating &
Cooling
Automatic
Pendulum Return
Automatic
Specimen Transfer
Percent Shear,
Lateral Expansion, Notch Verification
Digital Optical Comparator
Hardness
Testing
Charpy Data
Fitting
Circuit
Board Testing
Beverage Can Tester
Tongs
Shock Testing
Refurbished Equipment
MultiPurpose
Corrosion Cell
High Temperature
Reference
Electrode
Pressure Vessel
Manufacture
Pre-Owned
Equipment
Buy and
Sell
Analytical
Services
Finite
Element/Fracture
Mechanics
Neutron Transport
Analysis
P-T Curve
Analysis
Experimental
Services
Mechanical
Property Testing
Surveillance
Capsule Testing
Failure
Analysis
Services
Failure Analysis
News &
Information
MPM
Product
News
Directions to MPM
Nuclear News
| |
 
Introduction
Nuclear power plants contain surveillance capsules with neutron dosimeters
and mechanical property test specimens. These capsules are pulled
periodically throughout the life of the plant to monitor the properties of the
pressure vessel. When the capsules are analyzed, a neutron transport
analysis is performed to determine the neutron fluence to the capsule and the
vessel and to compare the calculated results with the dosimetry measurements.
In addition, neutron transport analyses are needed in other cases where the
fluence to a primary system component may affect the in-service performance of
the component. Examples include BWR shrouds and PWR vessel internal
components.
Transport Model Description
MPM capabilities include calculation of neutron transport for a wide variety
of geometries of interest. For typical cases where the locations of
interest are within the reactor beltline region, synthesis of two dimensional
calculations can be carried out using discrete ordinates transport methods.
The DORT code is selected for these analyses because of the ease of use, speed
of calculations, and routine acceptance by the Nuclear Regulatory Commission
(NRC). MPM uses the latest cross section libraries and the calculations
fully satisfy the requirements of NRC Regulatory Guide 1.190, "Calculational and
Dosimetry Methods for Determining Pressure Vessel Neutron Fluence". In
more complex cases, three dimensional discrete ordinates or Monte Carlo
transport calculations can be carried out.
Back to Top
|
| Search |
Contact Us