Studvik ScandpowerChristian Jönsson, Erin WehlageMay 29, 2017, Sunlight Hotel and Conference

Overview Studsvik Scandpower• Who is SSP

• Nuclear tradition

• Fuel Life Cycle – Software and services

• Global presence

Content

Studsvik 70th AnniversaryMay 29, 2017 2

• Reactor Core Analysis Software & Services• Over 700 man-years experience in the Nuclear Industry

• Fuel vendors• Utilities• Nuclear Power Plants• National Labs• Safety Authorities• Universities

• ~34 Nuclear Engineers & Staff(Ph.D., M.S.)

• Offices world-wide:(U.S., Sweden, Germany, Japan, China)

Who is Studsvik Scandpower?

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Studsvik’s Nuclear Tradition• 1947 founded as AB Atomenergi

• State-owned with private industry participation• Mission to develop, build and operate nuclear power plants

• Key player behind ”Swedish” reactor line• 1961: R2 (MTR) commissioning in Studsvik site• 1963: R3 commissioning (D2O, nat.U, 70 MWth)• 1960: Development of R4 (BHWR)• 1968: Creation of ASEA-Atom to build Swedish BWRs• 1970: Sweden signs NPT, D2O line abandoned• 1970-74: KRITZ critical experiments• 1972: Oskarshamn 1 starts operation• 1976: First CASMO• 1981: Studsvik of America, Inc. (Malte Edenius)• 1984: Newton,MA Office established• 1986: CASMO-3/SIMULATE-3• 1988: Idaho Falls, ID Office established• 1995: CASMO-4, SIMULATE-3K (Kinetics) • 1996: SIMULATE-3R (Real-time Training Simulators)• 1996: Västerås, Sweden office established• 1998: Merger with Scandpower Nuclear Div. Studsvik Scandpower Inc. (SSP)• 2001: (May 4) Studsvik AB listed on Stockholmborsen’s O list• 2005: R1 (50 MW) and R2-0 (1 MW) reactors decommissioned• 2007: Wilmington, NC office established• 2008: CASMO5 (Idaho Falls)• 2009: SIMULATE5 (Waltham/Västerås)• 2010: Newton,MA office moves to Waltham, MA• 2016: SSP Quality Assurance Program moves from Waltham, MA to Idaho Falls, ID• 2016: SSP Shanghai China Office

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Balance between: - Fuel development

- Computer speed

- Economy

- User/reviewer ”easy-to-use” perspective

- Level of details

- Generalization

Software for Nuclear fuel/core optimization & surveillance – What does it require?

Taking into account: - Pragmatic solutions

- ”right level of details”

• 1955 – 1975: First Generation LWR Analysis Methods• US Nuclear Navy Propulsion Program

• General understanding of neutron cross sections (interaction probabilities), neutron transport, cooling of nuclear fuel with high pressure water

• Development of the commercial PWR and BWR

• Computer memories only 0.5 Megabyte• 2-D diffusion calculations completely consumed the memory of the machines of that time

• 1 cycle depletion calculation in 2-D consumed an entire night of CPU time

• 3-D calculations beyond available memory and computing speed of the very best computers of that time

• PWR and BWR’s required separate methods for reactor analysis

Historical Perspective on the Development of Studsvik’sCore Management System

• 1975-1983: Second Generation LWR Nodal Method Development• KWU (Germany), MIT and the University of Illinois (U.S.) developed “Advanced Nodal Methods” that

allowed 3-D diffusion problems to be broken down into 1-D problems• Large 3-D diffusion problems could now be solved accurately with a factor of 1000x less computational effort

• 1978: Development of Studsvik’s (Sweden) CASMO lattice physics code started by Dr. Malte Edenius• His novel idea was to develop an accurate, fast running lattice physics code to solve 2-D neutron transport

problems

• The same code could be used for production analysis of BOTH PWR and BWR lattices (idea rejected by industry)

• 1984-1985: Development of SIMULATE-3 at Studsvik• Advanced computing techniques were incorporated to reduce computer storage and CPU

• First advanced nodal code that could be run successfully on a PC

• Could run 3-D BWR and PWR nodal calculations in only a few minutes

• Swedish focus on user convenience in analysis tools and automated engineering functions

Historical Perspective on the Development of Studsvik’sCore Management System (Continued)

• 1990: Development of Transient SIMULATE-3K with Studsvik’s own thermal-hydraulic model• Performs a wide range of safety analysis for both PWRs and BWRs

• 1995: XIMAGE was developed as Studsvik’s first graphical wrapper and optimization module around SIMULATE-3• Engineers could now evaluate 100,000+ core designs overnight with the fully automated reload core

optimization module

• 1997: Real-time version of SIMULATE-3K developed called SIMULATE-3R• First “engineering-grade” simulator model to be incorporated in plant operator training simulators

Historical Perspective on the Development of Studsvik’sCore Management System (Continued)

SIMULATE-3K Transients Safety

XIMAGE Optimization GUI

SIMULATE-3R Real-time Simulation

1990

2000

• 1998: Studsvik – Scandpower merger

Historical Perspective on the Development of Studsvik’sCore Management System (Continued)

Studsvik SIMULATE

Scandpower Core

Monitoring & Database

GARDEL On-line core monitoring

system

• 2000’s: Development of diverse product applications

Historical Perspective on the Development of Studsvik’sCore Management System (Continued)

• SNF (Spent nuclear fuel) program that uses CASMO and SIMULATE core data to produce 3-D nuclear fuel isotopics and calculates decay heat

Significant advancement over the traditional 1-D ORIGEN analysis

• MARLA graphical environment for BWR refueling schedule optimization, PWR fuel pool rack assessments and surveillance and cask loading optimization for both PWRs and BWRs

Balance between: - Fuel development

- Computer speed

- Economy

- User/reviewer ”easy-to-use” perspective

- Level of details

- Generalization

Software for Nuclear fuel/core optimization & surveillance – What does it require?

Taking into account: - Pragmatic solutions

- ”right level of details”

Studsvik Mission: - Create software with the ”right” level

of details for up-to-date fuel and core optimization goals

- Be independent of fuel/reactor vendors

- Be close to the customers!

- Know your history and prepare for the future!

- Always develop!

New CMS5 Environment

Studsvik Scandpower 2017 and Beyond• CMS5 (New versions: CASMO5 & SIMULATE5)

• Generic NRC license for CMS5 by end of 2017 to save customers ~ 1 million dollars USD/cycle

• New graphic user interface for design and output data analysis

• CMS-VVER (Under development, completed early 2018)• Targeting emerging Eastern European nuclear market => INCREASING THE CMS PWR COMMUNITY

Countries of Studsvik Scandpower CustomersArgentinaBulgariaChina (PRC)Czech Rep.FinlandFranceGermanyHungaryJapanItalyKorea Mexico

NorwayRussiaSlovakiaSpainSwedenSwitzerlandTaiwanUkraineUnited KingdomUnited States>60 Companies as customers

Over 200 PWR/BWR Reactors> 2000 PWR/BWR Cycles Analyzed

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SSP Customer Spectrum

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(Partial list)

Studsvik Scandpower nuclear fuel lifecycle capabilities

Fuel front endFuel vendor qualificationFuel bid requirement specifications and evaluations

Optimized fuel and core designs to provide the best economic valueReduce risk, ensure regulatory complianceAdvanced reactor design and testing

Optimum fuel performance

and core design

Core management,

operational support

Integrated product line: same model for core monitoring and real-time training simulatorAutomated reactivity management for efficient plant operation

Spent fuel management

Competence Development

Optimize use of spent fuel poolsDefuel pool at earliest possible dateSpent fuel cask optimization, management and procurement

High fidelity tools for automated analysis and visualizationEasy to use inputs and tools for developing reactor engineersAdvance software training

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• Smith, Kord S. “A Historical Perspective on the Development of Studsvik’s Core Management System”, ATS Ydintekniikka Journal of Nuclear Technology, Vol. 38, 2009.

More information on Studsvik Scandpower CMS Development