Radiological Dose, Shielding and Equipment Qualification

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One of Bostelman Engineering’s (BE) capstone areas of consulting is performance of radiological dose, shielding and equipment qualification evaluations. Our team routinely performs radiological dose assessments for humans and equipment as a result of normal and abnormal conditions of plant operations. We also have performed extensive accident assessments for various utilities related to predicting accident dose conditions at site boundaries. This work has been performed for US and International clients and has set us apart in regards to services that can be provided based upon our years of experience in radiation protection, design, fuels, and core operations. We serve as leaders in the industry by also providing annual training in radiological engineering each year. Our team routinely has the capability to promptly assess changing radiation environments, or look for potential release paths not previously considered. We have developed source terms for various radiological assessments based upon industry codes and standards.

Some of our team also serves on standing committees related to radiological engineering areas, and hold national certifications in this area. We address foremost the need for protection of the public and sensitive components when evaluating shielding and containment systems. We utilize real world operating experience from the field to address various and unique radiological conditions. Our emphasis on equipment qualification encompasses looking at test results, comparison evaluations to establish thresholds for operation or replacement. We also are qualified to perform shielding evaluations for hospitals related to diagnostic X-rays and for nuclear materials.

Areas of Focus

  • Shielding Evaluations
  • Dose Calculations
  • Dose Monitoring
  • Equipment qualification
  • Fuel Source term development
  • Accident Radiological dose predictions at site boundaries and control room
  • Decommissioning spent fuel pool source term and dose modeling

Qualifications

  • BE personnel train commercial nuclear industry on radiological engineering methods
  • BE personnel certified health physicist and serve on ANS standing committees
  • BE personnel certified to perform source term development
  • BE personnel certified to perform radiological dose calculations
  • BE personnel certified State of Nebraska to perform shielding evaluations for Medical Facilities
  • RADTRAD instructor since 1998

Code Experiences

  •  RADTRAD 3.03, 3.10 (Code Expert and User Group Trainer) site boundary and control room dose modeling, Simplified Model for RADionuclide Transport and Removal And Dose Estimation RADTRAD 3.03, 3.10 (Code Expert and User Group Trainer) site boundary and control room dose modeling, Simplified Model for RADionuclide Transport and Removal And Dose Estimation
  • URI-RASCAL emergency planning radiological release
  • MCNP* dose modeling at site boundary
  • SCALE* v. 6.2/ORIGEN-S, ORIGEN-ARP source term development tool to generate isotopic analysis
  • MicroShield™ code to perform Shielding calculations and evaluations
  • MicroSkyshine™ code to perform impacts of radiation shine to point locations

Previous Relevant Projects

Project: RADTRAD Training

  • Clients: Nine Utilities, NSSS Vendor
  • Tasks Completed: Training of RADTRAD computer code for accident dose calculations

Project: Alternative Dose Calculations

  • Client: Commercial Nuclear Unit**
  • Tasks Completed: Update all Accident Dose calculations as a result of new source term. Included performing equipment qualification radiological dose exposure calculations. Included evaluations of shielding calculations. Required running RADTRAD, MicroShield™ cases to generate post-accident doses, and equipment integrated doses

Project: Alternative Dose Calculations

  • Client: Commercial Nuclear Unit**
  • Tasks Completed: Third Party Review of dose calculations

Project: Dose Calculation from HELB

  • Client: Commercial Nuclear Unit**
  • Tasks Completed: Perform ORIGEN and MCNP calculations to derive gamma dose rate as a result of different HELB configuration. Also derived Beta source term to be evaluated for equipment qualifications.

Project: Dose Calculations from Fukushima Loss of Spent Fuel Pool Cooling

  • Client: Commercial Nuclear Unit**
  • Tasks Completed: Calculate dose as a result of pool boiloff related to beyond design basis events. Utilized for equipment qualifications of FLEX equipment and spent fuel pool level instrumentation. Utilized MicroShield™ and MicroSkyshine™ for dose calculations.

Project: Dose Calculations as a result of Loss of Spent Fuel Pool Cooling SAFESTOR condition

  • Client: Commercial Nuclear Unit**
  • Tasks Completed: Calculate source term for core offload gamma, neutron, and decay heat from ORIGEN runs. Also calculated source term from fuel stored in pool. This task output was then used to create MCNP runs for dose projections at EAB and LPZ as a result of pool boiloff. The subsequent calculations for decay heat were used further Zirconium fire calculations. The MCNP dose rate calculations were used for NRC submittal information. Subsequently USNRC approved the submitted information regarding zirconium fire and dose calculations.

Project: Dose Calculations with Inoperable Containment Monitors

  • Client: Commercial Nuclear Unit**
  • Tasks Completed: Perform dose calculations to estimate dose rate outside of containment post-accident. Provided information relevant for radiation monitoring with other monitoring devices.

Project: Owner Acceptance Reviews

  • Client: Commercial Nuclear Unit**
  • Tasks Completed: Preview EPU radiological calculations on behalf of client and coordinate resolution.

Project: Calculate EPU source term for Equipment Qualifications

  • Client: Commercial Nuclear Unit**
  • Tasks Completed: Generate scalars for EPU for dose rates and integrated doses of equipment post-accident and for normal plant operations.

*Denotes National Laboratory codes
**Further details can be provided by contacting us

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