Studvik Scandpower Christian Jönsson, Erin Wehlage May 29, 2017, Sunlight Hotel and Conference

Content

Overview Studsvik Scandpower • Who is SSP • Nuclear tradition • Fuel Life Cycle – Software and services • Global presence

May 29, 2017 Studsvik 70th Anniversary 2 Who is Studsvik Scandpower? • Reactor Core Analysis Software & Services • Over 700 man-years experience in the Nuclear Industry • Fuel vendors • Utilities • Plants • National Labs • Safety Authorities • Universities • ~34 Nuclear Engineers & Staff (Ph.D., M.S.) • Offices world-wide: (U.S., , , Japan, China)

Proprietary 3 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

Proprietary 4 Software for Nuclear fuel/core optimization & surveillance – What does it require?

Balance between: Taking into account: - Fuel development - Pragmatic solutions - Computer speed - ”right level of details” - Economy - User/reviewer ”easy-to-use” perspective - Level of details - Generalization Historical Perspective on the Development of Studsvik’s Core Management System

• 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’s Core Management System (Continued)

• 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’s Core 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

2000

SIMULATE-3R 1990 Real-time XIMAGE Simulation Optimization SIMULATE-3K GUI Transients Safety Historical Perspective on the Development of Studsvik’s Core Management System (Continued) • 1998: Studsvik – Scandpower merger

Studsvik SIMULATE GARDEL On-line core monitoring system Scandpower Core Monitoring & Database Historical Perspective on the Development of Studsvik’s Core Management System (Continued) • 2000’s: Development of diverse product applications

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

Balance between: Taking into account: Studsvik Mission: - Fuel development - Pragmatic solutions - Create software with the ”right” level of details for up-to-date fuel and core - Computer speed - ”right level of details” optimization goals - Economy - Be independent of fuel/reactor - User/reviewer ”easy-to-use” perspective vendors - Level of details - Generalization

- Be close to the customers!

- Know your history and prepare for the future!

- Always develop! 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 New CMS5 Environment Countries of Studsvik Scandpower Customers Argentina Norway Bulgaria Russia China (PRC) Slovakia Czech Rep. Spain Finland Sweden France Switzerland Germany Taiwan Hungary Ukraine Japan >60 Companies as customers Italy Over 200 PWR/BWR Reactors Korea > 2000 PWR/BWR Cycles Mexico Analyzed

Proprietary 13 SSP Customer Spectrum (Partial list)

Proprietary 14

Studsvik Scandpower nuclear fuel lifecycle capabilities

Fuel vendor qualification Fuel front end Fuel bid requirement specifications and evaluations

Optimized fuel and core designs to Optimum fuel provide the best economic value performance Reduce risk, ensure regulatory and core compliance design Advanced reactor design and testing

Integrated product line: same model Core for core monitoring and real-time management, training simulator operational support Automated reactivity management for efficient plant operation

Optimize use of spent fuel pools Spent fuel Defuel pool at earliest possible date management Spent fuel cask optimization, management and procurement

High fidelity tools for automated analysis and visualization Competence Easy to use inputs and tools for Development developing reactor engineers Advance software training

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