MCNP Case Study – Dry Cask Shielding

Tuesday, March 28th, 2017

We were contracted to build a complete Dry Cask shielding package for a BWR plant that had never done a Dry Cask campaign before and who was using a storage system that had never been used at a BWR before. The design challenge was to work within a given weight limit and provide the maximum dose reduction possible without adding any weight to the work platform.


Neutron Shielding – Borated Polyethylene

Wednesday, August 31st, 2016

Borated Polyethylene is NPO’s primary shielding material for reducing Neutron radiation.

Braidwood Survey

Braidwood Dry Cask Annulus Gap Snakes

Thursday, June 9th, 2016

Braidwood experiences significant dose reductions with their most recent dry cask campaign utilizing NPO shielding.


Lower Dry Cask Barrel Shield

Wednesday, March 9th, 2016

Our newest project shields the bottom 9 feet of a Dry Fuel Transfer Cask. It provides a HVL for neutron and gamma radiation and includes a 2 over 1 seismic analysis.


NPO uses MCNP to simulate Dry Cask

Wednesday, March 9th, 2016

MCNP (Monte Carlo N-Particle) was developed by Los Alamos National Laboratory to simulate nuclear processes for criticality safety, accelerator target design, reactor design, etc. NPO employs the expertise of our affiliate, PG Research Foundation, and MCNP code to solve shielding problems with complex sources and/or geometry such as Dry Cask processing. MCNP analyzes radiation spectrums in a 3D environment to produce numerous outputs including dose rates (mRem/hr) before and after shielding.