Responding to Fukushima: Real-Time, Interactive, Beyond Design Basis Modeling for SAMG, PRA and Training

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Presented at The Nuclear Training and Simulation China Forum in Beijing. This presentation discusses the use of interactive modeling and simulation to address post-Fukushima nuclear workforce training challenges. For more information, go to www.gses.com or call 800-638-7912. You can also follow GSE Systems on Twitter @GSESystems and on Facebook.com/GSESystems. Thanks for viewing!

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Responding to Fukushima: Real-time, Interactive, Beyond Design Basis Modeling for SAMG, PRA and Training

info@gses.com

2

I. Industry changes, drivers, challenges

II. Desktop simulator

III. Examples of PWR and BWR

IV. Applications and Flexibility

V. Conclusions

Outline

3

Changes Affecting Training

• Emergency response organization (ERO) staffing changes

• Knowledge, skills and proficiency requirements

• Severe accident management guideline (SAMG) changes

• Extensive damage mitigation guideline (EDMG) changes

4

• Post-9/11 revisions to NUREGs/FEMA REP

• Post-Fukushima initiatives

– NEI 12-01 – Guideline for assessing beyond design basis accident response staffing and communications capabilities

– NEI 12-06 – Diverse and flexible coping strategies (FLEX) implementation guide

– INPO IER 13-10 – Nuclear accident at the Fukushima Daiichi nuclear power station

– US NRC SECY-11-0124 - “Recommended actions to be taken without delay from the near-term task force report”

Change Drivers

5

Challenges for Industry

• Near-term challenges– Develop, write, train and drill on new SAMG/EDMG

processes and procedures– Install, maintain, train and drill on FLEX equipment– Increase in number of staff needing training/drills– Multiple-unit scenarios with single-unit simulators– More challenging PRA/PSA

• Long-term challenges– SBO and beyond DBA scenarios– Limited simulator capabilities– Integrated training of NOP, EOP, SAMG and EDMG

6

GSE Desktop Simulator

• Used by EPRI and ERIN Engineering to demonstrate capability of MAAP5 computer code “Modular Accident Analysis Program”

• Users easily interact with equipment controls and code models through modern human-machine interface

• Interface with plant DOSE model to project offsite DOSE

• Users visually observe the event unfolding via graphical depiction of scenarios

7

GSE Desktop Simulator

• Take plant data and run myriad SAMG/EDMG scenarios

• Simulate parallel events in multiple units

• Provide “what if” analysis of user-interactive actions and resulting consequences

• Provide interactive access to all model internal variables

• Assist with verification/validation of results against plant data

• Collect, assimilate and report a large amount of data

8

Unit 2Containment

MAAP5

RCS

MAAP5

SG

MAAP5

Core

Unit 1Containment

MAAP5

RCS

MAAP5

SG

MAAP5

Core

In-plant DOSE simulation

In-plant DOSE simulation

Ex-plant DOSE simulation

MAAP5

Auxiliary BuildingMAAP5

Spent Fuel Pool

PWR with 2 Units and Spent Fuel

9

Reactor Core

Unit 1 Unit 2 Time 4:2:56

10

Containment and Flammability

Time 4:2:56

11

Off-Site Radiological Dose

Time 6:20:06

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Multi-Unit Displays

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Vessel Failure – Unit 1

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Core Melt – Unit 2

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Core Melt – Unit 3

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Applications

Can be:– Run as stand-alone machine for individual use– Synched with other desktop simulators– Controlled/managed by an instructor– Used for training as individuals or teams

17

Flexibility and Growth

• Can add additional modules, such as:– Balance of plant– ECCS– Electrical– Main steam– Main feed water– MIDAS, RASCAL

• Advanced 3D visualizations coupled with simulation models can be added to inform the user of conditions inside containment and reactor during severe accident scenarios

• Can integrate with your simulator

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Conclusions

• Provides cost saving and lessens burden imposed by regulations

• Allows frequent and realistic training

• Uses the most advanced analysis models as daily training tools

• Backed and supported by reputable engineering/simulator teams

• Streamlines data communications

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Conclusions

• Prepares personnel– Supports operational decision making to support

transient analysis

• Supports development and implementation of challenging and realistic drills

• Does not require plant simulator time

• Supports remote training

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EPRI MAAP Code

• ''MAAP 5.0 is an Electric Power Research Institute (EPRI) software program that performs severe accident analysis for nuclear power plants including assessments of core damage and radiological transport. A valid license to MAAP 5.0 from EPRI for customer's use of MAAP 5.0 is required prior to a customer being able to use MAAP 5.0 with [LICENSEE PRODUCT].

• EPRI (www.epri.com) conducts research and development relating to the generation, delivery and use of electricity for the benefit of the public. An independent, nonprofit organization, EPRI brings together its scientists and engineers as well as experts from academia and industry to help address challenges in electricity, including reliability, efficiency, health, safety and the environment. EPRI does not endorse products or services, and specifically does not endorse [NEW PRODUCT NAME] or GSE. Interested vendors may contact EPRI for a license to MAAP 5.0."

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Thank you!

GSE Systems, Inc.

For more information:

Go to: www.GSES.com

Call: 800.638.7912

Email: info@gses.com

Follow us on:

Twitter @GSESystems

Facebook.com/GSESystems

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