The document provides an overview of the Stream Control Transmission Protocol (SCTP). SCTP is a connection-oriented transport layer protocol that offers reliable data transfer over IP networks. It supports features like multihoming for network fault tolerance, multi-streaming to minimize delay, and congestion control. The document discusses SCTP's architecture, features, security mechanisms, and error handling. It is intended to help application developers write programs using SCTP socket APIs.
This document summarizes a benchmark analysis of start-up physics tests performed at the High Temperature Engineering Test Reactor (HTTR). The analysis evaluated cold critical configurations, excess reactivity measurements, shutdown margins, axial reaction rates, and isothermal temperature coefficients. Some challenges included limitations in available public data and conflicting reported values. Overall, there was generally good agreement between benchmark measurements and calculations, though calculations were approximately 2% higher, likely due to uncertainties in graphite composition and cross sections. Completed benchmarks from this analysis will be published in the International Handbook of Evaluated Reactor Physics Benchmark Experiments.
This document provides an overview of the User Datagram Protocol (UDP). It discusses UDP's attributes that make it suited for certain applications like streaming media. It describes UDP's packet structure including header fields like source/destination ports and checksum. It also compares UDP to the Transmission Control Protocol (TCP), noting that UDP does not guarantee delivery or ordering while TCP provides reliability. The document provides examples of applications that commonly use UDP like DNS and VoIP.
Stream Control Transmission Protocol (SCTP) - IntroductionLaili Aidi
The document discusses the Stream Control Transmission Protocol (SCTP), a transport layer protocol that provides reliable message delivery like TCP but with some improvements. SCTP supports multi-homing where an endpoint can be associated with multiple IP addresses simultaneously. It also supports multi-streaming within a single association to reduce head-of-line blocking. SCTP uses a four-way handshake for connection setup and ensures reliable data transfer using transmission sequence numbers and selective acknowledgements.
This document provides an overview of the Stream Control Transmission Protocol (SCTP). SCTP was developed to provide reliable message transmission with built-in multi-homing and multi-streaming capabilities. It addresses some limitations of TCP and improves resistance to denial-of-service attacks. SCTP supports features like message-based communication, multi-homing for redundancy, multi-streaming for increased throughput, and reliable data transfer. It defines message and acknowledgement chunks, as well as procedures for association setup and shutdown. SCTP is supported on Linux and other operating systems and can be used as an alternative to TCP in telecommunications and other applications.
Domain Name System (DNS) is a hierarchical distributed database that contains mappings of domain names to IP addresses. DNS allows easy to remember domain names to be used instead of hard to remember IP addresses. It works by matching domain names to IP addresses through a lookup process involving root servers, top-level domain servers and authoritative name servers. This allows computers all over the world to communicate with each other using domain names.
User Datagram Protocol (UDP) is a connectionless protocol that provides datagram socket services. It is simpler than TCP with less overhead but does not guarantee delivery or order of packets. The Java API provides the DatagramSocket and DatagramPacket classes to send and receive data packets. A MulticastSocket subclass of DatagramSocket allows sending data to multiple recipients by joining them to a multicast group.
SNMP (Simple Network Management Protocol) allows network devices to be monitored and managed. It defines an agent-manager architecture where agents run on devices and respond to requests from managers to retrieve or store management information. SNMP uses a management information base (MIB) and structure of management information (SMI) to define managed objects and their properties. Key SNMP components include versions 1 and 2, protocol data units (PDUs) like get, set, and trap requests, and error codes. SNMP traps allow agents to asynchronously notify managers of events.
Overview of SCTP (Stream Control Transmission Protocol)Peter R. Egli
Overview of SCTP (Stream Control Transmission Protocol), outlining the main features and capabilities of SCTP.
SCTP is a transport protocol that overcomes many of the shortcomings of TCP, namely head-of-line blocking and stream-oriented transmission.
SCTP supports multiple streams within a connection and preserves boundaries of application messages thus greatly simplifying communication.
Additionally, SCTP supports multi-homing which increases availability in applications with high reliability demands.
SCTP inherits much of the congestion, flow and error control mechanisms of TCP.
SCTP has its roots in telecom carrier networks for use in transitional voice over IP scenarios.
However, SCTP is generic so that it is applicable in many enterprise applications as well.
This document discusses the User Datagram Protocol (UDP) which provides a connectionless mode of communication between applications on hosts in an IP network. It describes the format of UDP packets, how UDP checksums are calculated, and UDP's operation including encapsulation, queuing, and demultiplexing. Examples are provided to illustrate how a UDP control block table and queues are used to handle incoming and outgoing UDP packets. The document also discusses when UDP is an appropriate protocol to use compared to TCP.
UDP is a connectionless transport layer protocol that runs over IP. It provides an unreliable best-effort service where packets may be lost, delivered out of order, or duplicated. UDP has a small 8-byte header and is lightweight, with no connection establishment or guarantee of delivery. This makes it fast and low overhead, suitable for real-time applications like streaming media where resending lost packets would cause delay.
The document discusses the key features and mechanisms of the Transmission Control Protocol (TCP). It begins with an introduction to TCP's main goals of reliable, in-order delivery of data streams between endpoints. It then covers TCP's connection establishment and termination processes, flow and error control techniques using acknowledgments and retransmissions, and congestion control methods like slow start, congestion avoidance, and detection.
TCP is a connection-oriented, reliable transport protocol that provides stream delivery, connection-oriented, and reliable services. It uses sequence numbers, acknowledgment numbers, and other features like flow control, error control, and congestion control to reliably deliver data between two endpoints. A TCP connection involves three phases - connection establishment using a three-way handshake, reliable data transfer with acknowledgments, and connection termination with another three-way handshake or four-way handshake with half-close option. TCP works well for both low and high-speed networks.
This document provides an overview of the Simple Mail Transfer Protocol (SMTP). It discusses how SMTP clients and servers work, how messages are sent to SMTP servers using either relaying or DNS, the SMTP communication model involving connection establishment, message transfer, and connection termination. It also describes mail processing involving envelopes and headers, status codes, and special features like mail forwarding, gatewaying, and relaying. Limitations of SMTP are also noted.
The document discusses Telnet, a protocol that allows users to access remote computers. It provides an overview of Telnet's history and requirements, steps for connecting to a remote computer using Telnet, tips for its use, current applications, advantages of accessing systems remotely, and disadvantages of the text-based interface. The presentation concludes with thanks and references.
HTTP is the protocol that powers the web. It uses a request-response model where clients make requests that servers respond to. Common request methods include GET, POST, HEAD, PUT, DELETE, and OPTIONS. Responses include status codes like 200 for OK and content types. HTTP 1.1 added features like persistent connections and chunked encoding. Cookies are used to maintain statelessness. HTTPS uses SSL/TLS to secure HTTP connections with encryption, server authentication, and integrity.
The document discusses the Domain Name System (DNS) which maps domain names to IP addresses. It describes how DNS works hierarchically with a root server at the top level, below which are generic, country-specific and other domain levels. DNS servers store and distribute this mapping information across multiple computers to avoid a single point of failure. Primary DNS servers store and update zone files mapping domain names to IP addresses, while secondary servers transfer this information from primary servers.
Overview of the FTP protocol.
In the early days of the Internet, applications were mostly restricted to mail transfer (email) and file transfer. FTP (File Transfer Protocol) is one of the first standardized protocols for exchanging binary and text files between hosts.
FTP is rather simple in that it uses a TCP connection for exchanging commands and a data transfer TCP connection for the actual file transfer.
In normal FTP operation, the client opens the control connection to the FTP server while it is up to the server to open data connections for each file transfer. With the upcoming firewalls, this scheme proved to pose a problem since firewalls tend to block incoming TCP connections. Thus a passive mode was defined where the client is responsible to open the data connection to the server.
The document presents the Small Modular Advanced High Temperature Reactor (SmAHTR) concept being developed by Oak Ridge National Laboratory. The SmAHTR is a 125 MWt, integral, thermal spectrum fluoride salt-cooled reactor designed to produce both electricity and process heat up to 700°C initially with a future goal of reaching 1000°C. It employs a compact prismatic core with removable TRISO fuel stringers, uses passive decay heat removal systems, and is designed to be transportable.
- SmAHTR is a small modular advanced high temperature reactor concept being developed by Oak Ridge National Laboratory for electricity and process heat production.
- The preliminary design operates at 700°C with a future goal of 850-1000°C, has a thermal power of 125MW, uses TRISO fuel in a graphite core, and employs passive safety systems.
- Key design features include a cartridge core, integral primary system, LiF-BeF2 primary coolant, "two-out-of-three" intermediate heat transport and passive decay heat removal loops, and potential use of Brayton power conversion. The design aims to enable remote operations and truck transportability.
1. Metallic foam is a cellular metallic material with a porous structure and lower density than solid metal.
2. Metal foams are prepared using a liquid metallurgy route where a foaming agent is added to a metal melt, releasing gases during solidification to form pores. Common foaming agents include titanium hydride, zirconium hydride, calcium carbonate, and sodium carbonate.
3. An example process uses an aluminum alloy melt with 3.3% sodium carbonate as the foaming agent, producing a foam with 63% porosity and a density of 0.96 g/cc.
The document discusses cast iron sectional solid fuel boilers made by Solidmaster. It describes the boilers' cast iron sectional design, materials used, heating powers available in 6 models, corrosion resistance, air control systems, optional safety heat exchangers, combustion control options including thermoregulators and electronic boards, ash removal, and efficiency up to 75%. Tables provide specifications for 8 boiler models including section numbers, capacities, weights, dimensions and fuel types.
This document summarizes Columbian Chemicals' work with multi-wall carbon nanotubes (MWCNTs), called NanoBlackTM, for fuel cell applications. NanoBlackTM MWCNTs enable cost-effective, durable electrocatalysts like DURA-lyst® that show improved performance over traditional platinum catalysts. NanoBlackTM is also used to develop advanced gas diffusion layers and bipolar plates with enhanced properties for fuel cells.
This document provides specifications for three ceiling suspended cassette type indoor units - the FXUQ71MAV1, FXUQ100MAV1, and FXUQ125MAV1 - and their corresponding connection units BEVQ71MAVE, BEVQ100MAVE, and BEVQ125MAVE. It lists key details like cooling capacity, dimensions, fan motor output, sound levels, and standard accessories for each unit. Piping diameters and connection types are also specified. The units have microprocessor thermostats for temperature control and sound absorbing thermal insulation materials.
ppt on summer training Vardhman's Mahavir Spinning Mills Baddi (weaving devis...Bharat Rana
The document provides details about the operations at Mahavir Spinning including warping, sizing, and drawing processes. It lists the equipment used such as warping machines, sizing machines, and describes parameters like yarn counts, tensions, and temperatures. The summary also provides an organizational chart and contact details for the heads of different departments at the facility.
This document provides an overview of benchmarking experiments for criticality safety and reactor physics applications. It discusses benchmark experiment availability through demonstration databases and outlines the typical structure of a benchmark report, including experimental data, evaluation, modeling, sample calculations, and measurements. The document encourages student and young professional involvement in benchmark participation, which can provide educational opportunities, experience with computational analysis, and collaboration on senior design or thesis projects. Benchmarking cultivates engineering judgment and an analytical skill set that is valuable for nuclear professionals.
This document provides an overview and tutorial on benchmarking experiments for criticality safety and reactor physics applications. It discusses the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP), which provide benchmark models and data from critical and subcritical experiments. The tutorial demonstrates how to access and analyze benchmark reports from these projects, including how they are formatted and what type of experimental data and evaluations are typically included. Key sections of a sample benchmark report are dissected, such as the description of experimental configurations and materials, evaluation of data uncertainties, and derivation of the benchmark model. The purpose of conducting such benchmarking and evaluations is to support validation of nuclear data and computer codes used
This document provides an overview and tutorial on benchmarking experiments for criticality safety and reactor physics applications. It discusses the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiment Evaluation Project (IRPhEP), which maintain evaluated benchmark experiments. The document demonstrates the availability of benchmark experiments through the DICE and IDAT tools. It also dissects a sample benchmark report to illustrate the typical components, including experimental data, evaluation, benchmark model, sample calculations, and benchmark measurements. Finally, it provides an overview of benchmark participation and contributions by country to the ICSBEP evaluations.
This document provides an overview of benchmarking experiments for criticality safety and reactor physics applications. It discusses the benchmarking process used by the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP). The tutorial aims to demonstrate the databases used to access benchmark experiments - the International Criticality Safety Benchmark Experiment Data (DICE) and the International Data Bank for Reactor Physics Experiments (IDAT). It outlines the typical contents of a benchmark report, including experimental data, evaluation, benchmark model specifications, sample calculations and measurements. Participation in ICSBEP and IRPhEP is highlighted as a collaborative international effort.
The document summarizes benchmark evaluations of the NRAD reactor core conversion from HEU to LEU fuel. Key points:
- Benchmark models of the NRAD reactor were updated with new fuel composition data, reducing computational bias.
- Criticality and reactivity measurements for the 56- and 60-fuel element LEU cores were within uncertainty of calculations using MCNP.
- Future work includes additional startup tests with more fuel elements to further validate the LEU core performance.
1) The GROTESQUE experiment involved arranging small pieces of highly enriched uranium (HEU) metal into a complex geometric configuration on a steel diaphragm to achieve criticality.
2) Uncertainties in benchmark parameters like unit dimensions and positions resulted in negligible uncertainties in the calculated k-effective of less than 0.0001.
3) Radial position of units was identified as having the largest sensitivity, contributing an uncertainty of 0.0008 to k-effective.
The document summarizes benchmark tests performed on the NRAD reactor after its conversion from HEU to LEU fuel. Key points:
- Startup tests were conducted from March to June 2010 and included initial criticality, rod worth measurements, power calibrations up to 250kW.
- The 60-rod LEU core configuration has been added to benchmark databases and is available for criticality safety and nuclear data validation.
- Uncertainties in fuel parameters like uranium isotopic content contribute most to total experimental uncertainty of ±0.0027Δk.
- Simplifications made in the benchmark model like removing minor materials introduce small biases of +0.0012±0.0009Δ
This document discusses educating the next generation of nuclear criticality safety engineers through participation in international benchmark projects. It describes how evaluating benchmarks provides hands-on experience and enhances engineering skills for students. Benchmark analysis has been used to educate over 30 students in the past 25 years. Current student projects involve evaluating criticality safety and reactor physics benchmarks to develop critical thinking and judgment.
The MIRTE program conducted criticality safety experiments from 2008-2010 involving low-enriched uranium rod lattices reflected by or separated by various structural materials. MIRTE-1 experiments included configurations reflected by aluminum, glass, and water, as well as configurations with interacting arrays separated by large absorbing screens of various materials or thin absorbing plates. MIRTE-2 will continue experiments with new materials and potential modifications to the experimental device through 2013. Proprietary experimental data will be available to designated U.S. beneficiaries through non-disclosure agreements after 2017.
The document summarizes new and revised benchmark experiments included in the March 2011 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments. It describes 16 experimental series from 53 total series performed at 31 reactor facilities around the world. The benchmarks cover various reactor types including gas cooled, liquid metal fast, light water, heavy water, and others. Newly available or revised benchmarks include experiments from the High Temperature Engineering Test Reactor, Very High Temperature Reactor, SNEAK 7A/7B, ZPPR-9, -13A, -18C, IPEN/MB-01, LR-0, ZED-2, VENUS-9/1, RBMK, ZEB
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) accomplished the following in 2010:
1) Published the 2010 edition of the ICSBEP Handbook containing 25 newly approved benchmark evaluations.
2) Upgraded the ICSBEP database and user interface called DICE.
3) Approved 25 new benchmark evaluations from the United States and other countries covering a variety of experimental configurations.
The document discusses the development of benchmarks for the International Criticality Safety Benchmark Evaluation Project (ICSBEP). It describes the process for developing an ICSBEP benchmark, which includes describing the experiment, evaluating the data and uncertainties, specifying the benchmark model, providing sample calculations, and ensuring quality assurance. Benchmarks undergo rigorous internal and external review to be included in the ICSBEP Handbook, which contains over 500 evaluated experiments from 20 countries to validate nuclear data and computer codes.
1) Three HEU-beryllium experiments conducted at Oak Ridge in the 1960s were evaluated using modern computational tools to help validate models for a proposed Fission Surface Power system.
2) The experiments showed small biases of less than 0.5% Δk/k from computational models, indicating high quality data for validation.
3) Uncertainty analysis showed the new experiments would provide additional validation of computational models, especially for the beryllium reflector performance important for the Fission Surface Power design. The experiments helped reduce overall uncertainties in modeling fission reactors.
This document summarizes the International Handbook of Evaluated Reactor Physics Benchmark Experiments from March 2010. It describes 13 new or revised benchmarks from various reactor types including sodium-cooled fast reactors, lead-cooled fast reactors, very high temperature reactors, inert matrix fuel reactors, and others. The benchmarks support validation of computational methods for Generation IV reactor design and current light water, heavy water, and fundamental physics reactors. The handbook contains data from over 40 experimental series performed at 24 reactor facilities in 15 contributing countries and is available to OECD member countries and others.
This document summarizes a benchmark analysis of initial physics tests performed at the Fast Flux Test Facility (FFTF), a 400 MW sodium-cooled fast reactor. Key measurements included criticality, neutron spectra, control rod worths, temperature coefficients, and gamma/electron spectra. The benchmark model used MCNP5 simulations with some component homogenization. Most measurements showed good agreement with calculations, though rod worths were underestimated by 2-6% and below-core neutron spectra were impacted by homogenization. Future work includes developing a fully heterogeneous FFTF model and evaluating additional experimental data.
This document discusses providing nuclear criticality safety analysis education through benchmark experiment evaluation. It describes challenges in educating the next generation of nuclear criticality safety professionals without hands-on experience. Participating in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiment Evaluation Project (IRPhEP) provides opportunities for students to gain experience by evaluating benchmark experiments. Benchmark evaluations involve investigating experimental design and results, developing computational models, and participating in an international review process. This helps students develop analytical skills while cultivating good engineering judgment.
This document summarizes a criticality benchmark analysis of water-reflected uranium oxyfluoride slabs. It outlines the experiment background, evaluation process, results of the uncertainty and bias analyses, sample calculations comparing results using different nuclear data libraries, and current efforts to revise the benchmark. The benchmark evaluation assesses the minimum critical thickness of an infinite slab based on experimental data from 1955-1956. It analyzes uncertainties in parameters and simplifications of the model to determine bias. The detailed model results are within uncertainties of the simplified model, validating its use. An updated benchmark will be presented to the ICSBEP working group in 2010.
This document summarizes an analysis of criticality experiments performed with arrays of nested annular tanks containing highly enriched uranyl nitrate solution. The experiments were conducted in the 1980s at the Rocky Flats Critical Mass Laboratory and involved configurations with 1-6 tanks. Absorbing materials like borated concrete and cadmium plugs were also tested. MCNP models were developed and showed calculated eigenvalues were within 1-2 sigma of benchmark values. The results will be published in the International Handbook of Evaluated Criticality Safety Benchmarks.
This document summarizes an assessment of computational modeling capabilities for designing a fission surface power system for a lunar outpost. It was found that ENDF/B-VII nuclear data reduced biases compared to older data, except for subcritical and highly enriched uranium benchmarks. Beryllium reflector worth was found to have an increasing bias trend. Existing Zero Power Physics Reactor critical experiments were identified as able to validate the design without needing a new critical experiment. Uncertainty analysis found cross sections like beryllium (n,n) contribute significantly to uncertainty. Future work is outlined to further validate the design using benchmark experiments and reduce uncertainties.
Integrating Kafka with MuleSoft 4 and usecaseshyamraj55
In this slides, the speaker shares their experiences in the IT industry, focusing on the integration of Apache Kafka with MuleSoft. They start by providing an overview of Kafka, detailing its pub-sub model, its ability to handle large volumes of data, and its role in real-time data pipelines and analytics. The speaker then explains Kafka's architecture, covering topics such as partitions, producers, consumers, brokers, and replication.
The discussion moves on to Kafka connector operations within MuleSoft, including publish, consume, commit, and seek, which are demonstrated in a practical demo. The speaker also emphasizes important design considerations like connector configuration, flow design, topic management, consumer group management, offset management, and logging. The session wraps up with a Q&A segment where various Kafka-related queries are addressed.
kk vathada _digital transformation frameworks_2024.pdfKIRAN KV
I'm excited to share my latest presentation on digital transformation frameworks from industry leaders like PwC, Cognizant, Gartner, McKinsey, Capgemini, MIT, and DXO. These frameworks are crucial for driving innovation and success in today's digital age. Whether you're a consultant, director, or head of digital transformation, these insights are tailored to help you lead your organization to new heights.
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McKinsey's 4D Framework: Discover, Design, Deliver, and De-risk to navigate digital change effectively.
Capgemini's Framework: Focus on customer experience, operational excellence, and business model innovation.
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EuroPython 2024 - Streamlining Testing in a Large Python CodebaseJimmy Lai
Maintaining code quality through effective testing becomes increasingly challenging as codebases expand and developer teams grow. In our rapidly expanding codebase, we encountered common obstacles such as increasing test suite execution time, slow test coverage reporting and delayed test startup. By leveraging innovative strategies using open-source tools, we achieved remarkable enhancements in testing efficiency and code quality.
As a result, in the past year, our test case volume increased by 8000, test coverage was elevated to 85%, and Continuous Integration (CI) test duration was maintained under 15 minute
The Zaitechno Handheld Raman Spectrometer is a powerful and portable tool for rapid, non-destructive chemical analysis. It utilizes Raman spectroscopy, a technique that analyzes the vibrational fingerprint of molecules to identify their chemical composition. This handheld instrument allows for on-site analysis of materials, making it ideal for a variety of applications, including:
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Imagine being able to generate high-quality traffic and leads effortlessly. Sounds like a dream, right? Well, it’s not. It’s called LeadMagnet IQ, and it’s here to revolutionize your marketing efforts.
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Uncharted Together- Navigating AI's New Frontiers in LibrariesBrian Pichman
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The History of Embeddings & Multimodal EmbeddingsZilliz
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Communications Mining Series - Zero to Hero - Session 3DianaGray10
This is a continuation to previous session focused on Model usage and adapting for Analytics and Automation usecases. We will understand how to use the Model for automation usecase with a demo.
• Model Usage and Maintenance
• Analytics Vs Automation Usecases
• Demo of Model usage
• Q/A
1. Preliminary Benchmark
Evaluation of Japan’s High
Temperature Engineering
Test Reactor
John Darrell Bess
R&D Engineer – Reactor Physics
May 5, 2009
2. Objective
• The benchmark assessment of Japan’s High
Temperature Engineering Test Reactor (HTTR) is
one of the high priority activities for the Next
Generation Nuclear Plant (NGNP) Project and Very
High Temperature Reactor (VHTR) Program.
• Current efforts at the Idaho National Laboratory
(INL) involve development of reactor physics
benchmark models in conjunction with the
International Reactor Physics Experiment
Evaluation Project (IRPhEP) for use with verification
and validation (V&V) methods.
2
4. IRPhEP Handbook – 2009 Edition
• 15 Contributing Countries
• Data from 36 Experimental
Series – 21 Reactor Facilities
• Data from 7 reactor types – Up
to 8 types of measurements
• Data from 33 out of the 36
series are published as
approved benchmarks
• Data from 3 out of the 36 series
are published in draft form
• http://nuclear.inl.gov/irphep/
4
5. HTTR Primary Design Specifications - I
Thermal Power 30 MW
Outlet Coolant Temperature 850/950 ºC
Inlet Coolant Temperature 395 ºC
Primary Coolant Pressure 4 MPa
Core Structure Graphite
Equivalent Core Diameter 2.3 m
Effective Core Height 2.9 m Air cooler
Crane
3
Average Power Density 2.5 W/cm Refueling
machine
Fuel UO2
Enrichment 3 to 10 wt. %
Spent fuel
6 wt. % (average) storage pool
Fuel Type Pin-in-Block Type
Coated Fuel Particles
Burn-Up Period (EFPD) 660 days Reactor
pressure
Fuel Block Graphite Block vessel
Coolant Material Helium Gas Intermediate
heat exchanger
Flow of Direction in Core Downward
Reflector Thickness Pressurized
water cooler
Top 1.16 m
Side 0.99 m
Bottom 1.16 m
Number of Fuel Assemblies 150 Reactor containment vessel
Number of Fuel Columns 30
Number of Pairs of Control Rods
In Core 7
In Reflector 9
Plant Lifetime 20 years
5
9. Fuel and Burnable Poison Loading
The top The bottom
number of number
each block represents the
represents boron content
the uranium in the burnable
enrichment. poison pellets.
9
13. Uncertainty Analysis - I
• The uncertainty • All random
analysis consisted of uncertainties are
the perturbation of the treated as 25%
benchmark model systematic
parameters and a – The large number of
comparison of the components in the
computed eigenvalues reactor tend to
to determine the reduce random
effective uncertainty in uncertainties to
the model. negligible quantities
– This preserves some
of the uncertainty in
the HTTR model
13
14. Uncertainty Analysis - II
• Experimental measurements • Computational analyses
– Isothermal temperature – Room return effects
– Control rod positions – Stochastic modeling of TRISO
• Geometric properties – Random number generation
– Diameter – Instrumentation bias
– Height
– Thickness
– Pitch
• Compositional variations
– Fuel enrichment
– Material density
– Impurity content
– Boron absorber content
– Isotopic abundance of boron
Ordered Lattice Uniformly-Filled
– Clad composition
– Fuel Mass Benchmark Lattice
Configuration
14
15. Results
• The benchmark model eigenvalue, keff, for the fully-
loaded core critical was determined: 1.0025 ± 0.0070.
Computed Eigenvalues for the HTTR Benchmark.
Neutron Library Ordered Uniform Difference (C-E)/E
ENDF/B-V.2 1.0233 1.0231 0.02% 2.1%
ENDF/B-VI.8 1.0253 1.0237 0.16% 2.3%
ENDF/B-VII.0 1.0260 1.0242 0.18% 2.3%
JEFF-3.1 1.0271 1.0252 0.18% 2.5%
JENDL-3.3 1.0216 1.0200 0.16% 1.9%
15
16. Systematic vs. Random Uncertainty
0.014
Random Systematic Total
0.012
Maximum Total Uncertainty
0.010
0.008
0.006
0.004
0.002
0.000
0.00 0.25 0.50 0.75 1.00
Fraction of Random Uncertainty Treated as Systematic
16
17. Points of Interest - I
• The most significant contributions to the overall uncertainty
include the impurities in the IG-110 graphite blocks and PGX
graphite reflector blocks.
– -0.0131 ± 0.0003 ∆keff/ppm – IG-110 graphite.
– -0.0019 ± 0.0003 ∆keff/ppm – PGX graphite.
– Other ICSBEP/IRPhEP benchmarks demonstrate similar
sensitivities to graphite impurities.
• The influence of random uncertainty is negligible: <0.0005 ∆keff
– Dominant uncertainties are systematic in nature.
– Better characterization of these parameters will reduce the
overall uncertainty.
17
18. Points of Interest - II
• Calculated eigenvalues are 2 to 3% greater than
expected benchmark experiment values.
– Other ICSBEP/IRPhEP benchmarks have 1 to 2%
biases.
– Previous Japanese HTTR benchmarking efforts
also demonstrated 1 to 3% biases.
– This model is based on available public HTTR
data; much of the HTTR data is proprietary and
unpublished because the reactor is currently in
operation.
– The inclusion of more detailed HTTR data should
reduce the computational bias in the benchmark.
18
19. Current Efforts – Annular Core Criticals
• Current benchmark efforts include the analysis of the initial
core critical geometries generated during the initial fuel
loading of the HTTR.
– These core configurations involved the replacement of
dummy fuel graphite blocks with fueled assemblies.
– Configurations include the initial critical with 19 fuel
columns, a thin annular core with 21 fuel columns, two
cores with 24 fuel columns (one controlled with the central
control rods and the other with the reflector control rods),
and a thick annular core with 27 fuel columns.
– The fully-loaded configuration contains 30 fuel columns.
• The most significant contributions to the overall uncertainty
include the impurities in the IG-110 graphite blocks, PGX
graphite reflector blocks, and IG-11 graphite dummy blocks.
19
22. Annular Core Benchmarking Effort
Comparison of keff for HTTR Start-Up Cores
(MCNP5 with ENDF/B-VII.0)
1.035
Case 2
Case 4
Case 1
1.030
Case 3
1.025 Full Core
Case 5
1.020
1.015
keff ± 1σ
1.010
1.005
1.000
0.995
Uniformly-Filled Lattice Ordered Lattice Benchmark
0.990
18 20 22 24 26 28 30 32
Number of Filled Fuel Zones
22
23. Future Benchmark Analyses
• Reactivity measurements from the initial start-up core physics
tests
– Isothermal temperature coefficient
– Axial reaction rate distribution
– Kinetics measurements
– Shutdown margin
– Control rod worth
– Excess reactivity
• Hot zero-power critical
• Rise-to-power tests
• Irradiation tests
• Radiation shielding
• Safety demonstration tests
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24. Acknowledgments
• Funding for the HTTR benchmark was provided by
the INL VHTR Program.
• The author would like to acknowledge the time and
expertise provided by N. Fujimoto from the Japan
Atomic Energy Agency; Luka Snoj from the Jožef
Stefan Institute; Atsushi Zukeran, acting as Senior
Reactor Physics Consultant; and Blair Briggs,
Barbara Dolphin, Dave Nigg, and Chris White from
the INL, for review, preparation, and presentation of
the HTTR benchmark.
24