Projects Completed (year end 2008)
Oak Ridge National Laboratory has acquired PCTRAN new reactor model
MST has delivered a new reactor PCTRAN model to the national lab's Advanced Reactor Systems and Safety Group. ARSS provides a wide range of support for analyzing, modeling, and controlling reactor power systems. The lab is commissioned by the US NRC for reviewing all vendors' submittals of new reactor designs. With their expertise and resource, PCTRAN will evolve into a major analytical and simulation tool in the development of advanced reactor systems.
The Mexican Institute of National Nuclear Investigation has selected PCTRAN for its LaGuna Verde (GE BWR5) severe accident analysis. The package delivered also contains G3 models of AP1000, EPR, ESBWR, ABWR and TRIGA models
Pakistan Nuclear Regulatory Authority has selected PCTRAN for its Chasma (PWR 2-loop 300 MW) severe accident analysis. The package also contains G3 models of PWR 3-loop, EPR, AP1000 and off-site dispersion projection.
In 2006 PCTRAN has successfully added Calvert Cliffs (Constellation), FitzPatrick (Entergy Northeast), Beaver Valley and Limerick (for Pennsylvania DEP) and Tsuruga (JAPC in Japan) in its client list. A Gaussian plume and puff dispersion model is successfully integrated for projection of offsite dose. In addition, NRC has approved Constellation's submittal of Ginna's power upgrade using PCTRAN in PSA. Following is a brief outline:
Loss of RHR during Cold Shutdown Mid-loop Conditions for Turkey Point
Plant specific models of PCTRAN for the St Lucie and Turkey Point plants have been used over 20 years in FP&L. In 2006 the model is upgraded to analyze loss of RHR during cold shutdown mid-loop conditions. Boil-off to core uncovery time is studied for various combinations of equipment availability and operator actions. A new feature of fast replay can make lively visual presentation in place of dull transient plots.
PCTRAN-PWR used as course material in IAEA's Workshop
on Advanced Reactor Simulation in Bucharest, Romania, July 3-7, 2006. It is the ninth year the UN agency conducts the training workshop for member states. The workshop for 2007 will be held in Internation Center for Theoretical Physics (ICTP) in Trieste, Italy in October.
Taiwan Power Company has used a puff model with variable weather condition to its PCTRAN model to evaluate the total committed dose equivalent (TEDE) rate and integrated dose inside the emergency planning zone (5 km radius) from local atmospheric dispersion. The model assumes a quasi-steady state release of radioactive materials. Different scenario of the accident determines the consequences of the release. Atmospheric conditions, such as Pasquils conditions, wind speed and direction is the user inputs. A colored display around the emergency planning zone shows dose rate distributions.
Preparation of Calvert Cliffs model for Constellation Energy
A plant specific model of the C-E PWR plant Calvert Cliffs was completed for the Risk Engineering Department. It is used for PRA event tree consequence study. Details of the PWR plant's reactor protection system (RPS) and Emergecy Feature Actuation System (EFAS) are modeled and tested successfully. The tool has met Regulatory Guide 1.174 for providing support in risk-based Reactor Oversight Process.
Limerick and Beaver Valley Plant Models to State of Pennsylvania
The State Department of Environment Protection, Radiation Protection Bureau has selected two out of five nuclear plants in its Commonwealth as the first step to be equipped with its own computerized scenario generators. Acquisition of the remaining Peach Bottom, Susquehanna and TMI plant models are in planning
Severe Accident Simulator for Tsuruga 1 of JAPC
The largest nuclear power generation company in Japan has installed PCTRAN simulator for its GE BWR-2 plant. It is used for severe accident management (SAM) program. The model allows core melt, hydrogen generation, containment failure and corium-concrete-interaction. Management guidelines such as flooding, vent, and combustion gas control can then be tested in analysis or exercise. Benchmark against MAAP and SAFER codes are successful.
Spent fuel pool accident simulators for Entergy Northeast
After successful development of Indian Point (PWR) SFP simulator, the first BWR SFP simulator for FitzPatrick was completed. Given that SFP of Mark 1 is high above ground, a loss of coolant event either by mechanical failure or sabotage could be catastrophic. The simulator provides time estimate to potential zirconium fire and alternate mitigation means.
Ginna's Extended Power Upgrade
PCTRAN was used for justifying the success criteria determination in the event trees of the plant's PSA for a power upgrade from 1520 MWt to 1775 MWt. The core degration frequency (CDF) must not increase significantly for the power upgrade. The analysis was reviewed and endorsed by Westinghouse. NRC has since reviewed the submittal and approved the methodology and results.
US Naval Academy use of PCTRAN in its curriculum
The academy has acquired both a generic PWR power plant and an experimental pool reactor models for its midshipman's class of nuclear technology. Neutron multiplication, criticality, moderator and poison feedback, and power maneuvering can be demonstrated lively. It is used in classroom lecture and computer laboratory for both normal and transient nuclear operations.
Florida Power and Light Company St Lucie and Turkey Point Plants
Plant specific models of PCTRAN-Windows for the C-E St Lucie and Westinghouse 3-loop Turkey Point plants have been completed. Cases of small break LOCA, stuck open PORV and station blackout have been analyzed on consideration of core exposure timing (Division I of PRA). The Westinghouse Peer's Review Group for PRA success criteria determination reviewed the report.
NEAT/JNC of Japan (Now Japan Nuclear Energy Safety Organization)
In February of 2003, a license agreement was reached by introduction of CSA of Japan, Co, Ltd to license the code to Nuclear Emergency Assistance and Training Center (NEAT) of Japan Nuclear Cycle Development Institute (JNC). Training seminars have been conducted in March of 2003 at the two NEAT facilities in Tokai Village and Tsuruga city. PCTRAN PWR and BWR are used to support emergency planning for all 55 nuclear units in Japan. In 2006 the code was upgraded to include preset freeze and replay capabilities. It is currently under evaluation to have another upgrade to include offsite dose assessment feature.
KKG Goesgen in Switzerland Spent Fuel Pool
A KKG Goesgen (KWU 3-loop 900 Mwe PWR) spent fuel pool simulator was developed for the Swiss regulatory agency HSK. It has the capability of analyzing a “total destruction” with complete loss of cooling and coolant to the pool and making dose release estimate to the environment.
Omaha Public Power District Fort Calhoun
Plant specific models of PCTRAN-Windows for the C-E designed Fort Calhoun Plant was prepared in 2001. It is site-licensed for application in emergency preparedness, nuclear analysis, PRA and training (including severe accident management guidelines). In year 2002 it was expanded into core-melt and containment failure for severe accident management guidelines (SAMG). The model can handle hydrogen generation and burn following core exposure. In year 2007 OPPD has decided to upgrad again to expand to offsite dose assessment.
Atomic Energy Council of Taiwan
A contract work was awarded by the Taiwan government agency to prepare the Emergency Action Level (EAL) matrix according to Nulear Energy Institute (NEI) guideline NESP007. Accident scenarios generated by PCTRAN-Windows will be used in exercises with the symptom-oriented EAL matrix to determine the EAL classification.
Nuclear Power Corporation (NUPEC) of Japan
MST has won a contract to provide eight PCTRAN model types for analyzing all 55 light water reactor power plants in Japan. They are categorized into eight groups: Westinghouse/MHI PWR of 2, 3 and 4 loops with dry containment and 4-loop PWR with ice condenser containment, GE/Toshiba/Hitachi BWR3 and 4 with Mark I containment, BWR5 with Mark II containment and ABWR. The software will be used for analyzing thousands of event tree cases leading to core failure. It will also be used for generating source terms for dose release.
NPP Chinshan of Taiwan Power Company (GE BWR-4 Mark-I 600 MWx2) for Windows
NPP Kuosheng of Taiwan Power Company (GE BWR-6 Mark-III 2 x 900 MW) for Windows
In addition to NSSS and containment simulation, the source term and release pathways will be simulated and stored in a database in a network. It will be connected to dose dispersion software for offsite dose projection.
Guangdong NPP in Daya Bay, China (Framatome 3-loop 900 Mwe)
Has provided a plant specific PCTRAN Windows model for the Hong Kong government. Long-term maintenance and consultation contract has been awarded to provide assistance in emergency exercise and planning of radiological events.
NPP KKL Leibstadt (BWR-6 Mark III 1050 Mwe) for Windows
By arrangement of Colenco Power Service Ltd., a partner and distributor of MST in Switzerland, PC-based simulation software in Windows is prepared for the Swiss regulatory agency HSK. Training lesson and installation will be conducted in Switzerland in November 1999.
KWU-designed 3-loop PWR plant KKG (Goesgen)
The HSK project in DOS is updated to Windows in June 2000. The KWU plant has turbine run-back capability in the event of one recirculation pump trip or load rejection. Verification against previous analyses using RELAP5 has resulted in satisfactory agreement.
Westinghouse 2-loop PWR plant KKB (Beznau)
The Windows version of PCTRAN to HSK in November 2000. Verification against previous analyses has resulted in satisfactory agreement.
Lungmen Project ( 2 x 1300 MWe GE ABWR) in Taiwan
Taiwan Power Company granted a contract in the fall of 1997 to construct a Windows-based simulation system for the Fourth Nuclear Project in Lungmen. The system will be plant specific for the ABWR under construction with internal recirculation pumps and advanced safety systems. It will use Windows-based graphic user interface (GUI) with pull-down menus and mouse control.
NPP TVO-I/II Severe Accident Simulator for Windows
Contract was awarded to upgrade the severe accident simulator to Windows. It was delivered in March 2000.
DOS Versions prior to 1998
High Temperature Gas Cooled Engineering Test Reactor (HTTR) in Japan
By arrangement of IEAJ, MST's partner and distributor in Japan, A PC-based simulator for the 30 MW test reactor has been prepared and delivered to Japan Atomic Energy Research Institute (JAERI) in March 1998. The experimental reactor is graphite modulated and helium cooled device capable for raising the gas temperature up to 950?C. PCTRAN-HTTR predicted operating and transient data are in good agreement with JAERI's own analysis. The user-friendly devise may be used for training and public demonstration on advanced nuclear technology.
NPP Goesgen (KKG) and Muehleberg (KKM) in Switzerland
Through arrangement of Colenco Power Consulting, MST's partner and distributor in Europe, MST has provided the Swiss government regulatory agency HSK the plant specific models of the KWU-designed 3-loop PWR plant KKG in 1996, and the GE BWR in Muehleberg in 1998 for analytical applications. The KKM DOS model was completed in 1998 and the contract was extended to further develop a Windows version.
International Atomic Energy Agency
A contract was granted by IAEA starting 1996 to prepare Advanced Reactor Simulation training software and material for all its member states. The software is to introduce advanced reactor designs and demonstrate their normal and transient behavior. The reactor types cover advanced PWR, BWR, VVER, AP600 and PHWR. So far five training workshops have been conducted, in Egypt, Austria, Saudi Arabia, Italy and Korea.
Teollisuuden Voima Oy, Finland
Has provided a plant specific severe accident simulator for TVO I/II (ABB BWR). The model has capability to simulate core melt, vessel and containment failure, radiological release source terms and offsite doses. It is used for training and severe accident management beyond design basis events including core failure, containment flooding, vent filtration, etc. A 3-year maintenance extension is in effect.
Mitsubishi Heavy Industry, Japan
Has provided (in 1995) the generic PCTRAN/U simulation code and licensed the source code. MHI is in the process of developing an Operator Training Aid system in which PCTRAN's man-machine interface (using pull-down menu and icons) will be adopted. A royalty will be paid back to MST if MHI is successful in completing and marketing that product.
Japan Atomic Energy Research Institute
Has developed (in 1995) a PC-based simulator for the JAERI Passive Safety Reactor (JPSR), an advanced PWR design with once-through steam generators and passive ECCS. In 1998 MST has delivered the High Temperature Test Reactor (HTTR) simulator for the 30 MW helium gas reactor in Oraii. It was tested to perform consistently with JAERI's design codes.
Atomic Energy Commission of Indonesia
Has provided (in 1994) the generic PCTRAN/U code for training its technical staff and evaluation of nuclear safety on various types of PWR designs. Indonesia is in the process of selecting its first NPP type.
TUEV Rheinland in Germany
Has prepared the plant specific models for Wuergassen (BWR) and Muelheim-Kaerlich (ABB OTSG PWR).
NPP Brunsbuettel (KKB) in Germany
Provided the simulation code for the GE BWR Wuergassen.
NPP Stade (KKS) in Germany - Provided the generic PWR simulation code.
NPP Paks in Hungary - Provided the Soviet-designed VVER-440/213 plant with a simulation code.
NPP Krsko PWR 2-loop designed by Westinghouse in Former Yugoslavia (now Slovenia)
Previous Works:
Government: US Nuclear Regulatory Commission, (Reactor Systems Branch), Swiss Nuclear Regulatory Agency (HSK), New Jersey Department of Environemtn Protection Nuclear Safety Bureau, Training simulators for Oyster Creek, Salem and Hope Creek.
NPPs in US: Point Beach, Turkey Point, St. Lucie, Salem, Hope Creek, Duane Arnold, TMI-1, Oyster Creek, Grand Gulf, River Bend, Peach Bottom, Limerick, etc. in U.S.
NPPs overseas: Chinshan, Kuosheng and Maashan in Taiwan, Krsko in Yugoslavia, Vadellos 2 in Spain, Koeberg in South Africa, Laguna Verdi in Mexico, Borsele (EPZ) in Holland
Industry: IBM, Earth Tech (Concord, MA), Enercon Services (Tulsa, Ok), M&K Associates (Boulder, Co), Central Research in Electric Power Institute (CREPI in Japan)
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