Wir schaffen Wissen heute für morgen
|
|
|
- Ezra Norton
- 6 years ago
- Views:
Transcription
1 Wir schaffen Wissen heute für morgen Paul Scherrer Institut Gavillet Didier Division HOTLABOR (AHL) / The Hot Laboratory Core competences and projects
2 Outline of the presentation AHL / HOTLAB history and actual situation Mission / Strategy / Goals Core competences Highlights and Projects Conclusion PSI / AHL / GD43 / HOTLAB / Seite 2
3 PSI / AHL / GD43 / HOTLAB / Seite 3
4 HOTLABOR The HOTLAB was - designed in built between inaugurated in October licensed in 1964 (unlimited) - till 1988: part of EIR - from 1988: part of PSI Hot-Cells PSI / AHL / GD43 / HOTLAB / Seite 4
5 HOTLABOR PSI-Ost Aare HOTLABOR psi forum Auditorium PSI-West PSI / AHL / GD43 / HOTLAB / Seite 5
6 Legal Framework The renewal of the operational licence is on going The ENSI has completed the review of the safety report The process goes further with the Canton hearing and finally with the public hearing We expect a renewal of our license in about one year for now PSI / AHL / GD43 / HOTLAB / Seite 6
7 Legal Framework Open problems / difficulties: Missing Earthquake-resistance proof some refurbishment are needed Maximum inventory in the lab (limited due to the missing proof of the earthquake resistance) PSI / AHL / GD43 / HOTLAB / Seite 7
8 PSI / AHL / GD43 / HOTLAB / Seite 8
9 AHL Mission / Vision / Strategy AHL Vision / Mission safe and efficient operation of the Hot laboratory Swiss competence centre for the handling and analysing highly radioactive materials including nuclear fuel contributes to the safe operation of the Swiss power plans supports PSI and external research groups for the handling, the preparation and the analysis of radioactive specimens develops and improves its analytical methods in the interest of the users of the lab PSI / AHL / GD43 / HOTLAB / Seite 9
10 AHL Mission / Vision / Strategy AHL operational goals AHL pursue a safe and efficient operation of the hot laboratory AHL develops and imposes a good safety culture in the facility. AHL pursue the renewal of the operational license with an attractive material capacity PSI / AHL / GD43 / HOTLAB / Seite 10
11 AHL Mission / Vision / Strategy AHL scientific goals keep and improve its competences and the needed infrastructure for the scientific investigation of LWR fuel pin keep and improve its competences and infrastructure for the scientific investigation of radioactive materials develop new preparation and analysis methods to better support all user of the laboratory PSI / AHL / GD43 / HOTLAB / Seite 11
12 AHL Mission / Vision / Strategy AHL scientific goals develop its capacity to produce very small specimens at specific location out of highly radioactive materials (FIB) keep the capacity to handle, treat and analyze small amount of fresh fuel (reference material; confiscate, Test material, ) PSI / AHL / GD43 / HOTLAB / Seite 12
13 AHL Mission / Vision / Strategy AHL strategic goals be the Swiss competence center for the analysis of radioactive materials conducts research work in collaboration with other users of the laboratory or as partner in international research projects in order to improve and acknowledge its core competences stay attractive for young technicians and scientists PSI / AHL / GD43 / HOTLAB / Seite 13
14 PSI / AHL / GD43 / HOTLAB / Seite 14
15 AHL core competences Operation of a nuclear facility Safety culture Handling, investigation and conditioning of highly radioactive materials Preparation and analytical investigation of radioactive materials (structure, chemical composition, material isotopic composition, failure mechanisms, ) Readiness and flexibility for immediate support to nuclear operators in Switzerland PSI / AHL / GD43 / HOTLAB / Seite 15
16 Specificity of the Hot Laboratory The hot laboratory is a building with the specific infrastructure for insuring the safety and security for the handling and analysis of radioactive materials Specific Infrastructure Ventilation / under-pressure Water treatment / control Radioprotection Bookkeeping / Documentation Safety and Security PSI / AHL / GD43 / HOTLAB / Seite 16
17 Operation of the hot laboratory Operation Ventilators (Hot cells) Filter banks Water treatment Waste preconditionning PSI / AHL / GD43 / HOTLAB / Seite 17
18 Was ist eine HOTLABOR Special tools Hot Cell chain (cement) Lead or Steel cells Glove boxes Shielded analytic tools PSI / AHL / GD43 / HOTLAB / Seite 18
19 PSI / AHL / GD43 / HOTLAB / Seite 19
20 Organisation des PSI-HOTLABORs HOTLABOR-Users Operation Hot Cell Analysis of fuel rods Analyse of radioactive materials including nuclear fuels PSI / AHL / GD43 / HOTLAB / Seite 20
21 PSI / AHL / GD43 / HOTLAB / Seite 21
22 AHL Highlights / Projects Support for research Projects (MEGAPIE) Innovative processing / optimisation / safety and flexibility Scientific Service for Power Plant PIE of fuel rod. From reception to overcanning Radioactive Material analysis Detailed analysis of radioactive materials Development of new tools PSI / AHL / GD43 / HOTLAB / Seite 22
23 MEGAPIE Analysis and Specimen extraction in MEGAPIE Target (material behavior in liquid metal target) Sectioning in ZWILAG Specimen extraction in the hot laboratory at precise location Gamma mapping of the safety hull From LBE From steel PSI / AHL / GD43 / HOTLAB / Seite 23
24 MEGAPIE Gamma-mapping of the MEGAPIE safety hull (1Sv/h in 1cm in center) PSI / AHL / GD43 / HOTLAB / Seite 24
25 MEGAPIE Specimen extraction for LBE analysis Hotlab developed core drilling tool LBE specimen LBE LBE specimen with steel PSI / AHL / GD43 / HOTLAB / Seite 25
26 MEGAPIE LBE-removal out of MEGAPIE pieces (for structural material investigation) All LBE has been melted without large contamination of the cell (this has proven the efficiency of the release protection measures) PSI / AHL / GD43 / HOTLAB / Seite 26
27 MEGAPIE Tensile and TEM specimen preparation in steel Development of the cutting tool and safety measures EDM Machine PSI / AHL / GD43 / HOTLAB / Seite 27
28 Post Irradiation Analysis of fuel rods Transfer of fuel rod in the concrete Cell PSI / AHL / GD43 / HOTLAB / Seite 28
![Post Irradiation Analysis of fuel rods Non Destructive Analyses Total Activity [cps] γ-spektrometrie - Defect](/docs-images/74/70425506/images/29-0.jpg "rod 2600 2400 2200 2000 1800 TOTAL 1600 1400 CS134 CS137 RU106 CE144 NB95 1200 1000 800 600 400 200 0 0 1318")
![1320 1322 1324 1326 1328 1330 1332 1334 Elevation [mm] 200 180 160 140 120 100 80 60 40 20 Single isotope](/docs-images/74/70425506/images/29-1.jpg "Activity [cps] Visual inspection gamma spectrometry (defect fuel rod) PSI / AHL / GD43 / 27.03.")
29 Post Irradiation Analysis of fuel rods Non Destructive Analyses Total Activity [cps] γ-spektrometrie - Defect rod TOTAL CS134 CS137 RU106 CE144 NB Elevation [mm] Single isotope Activity [cps] Visual inspection gamma spectrometry (defect fuel rod) PSI / AHL / GD43 / HOTLAB / Seite 29
30 Post Irradiation Analysis of fuel rods Development of the needed tools Mirrors Fuel Rod Laser Unit PSI / AHL / GD43 / HOTLAB / Seite 30
31 Profilometry Post Irradiation Analysis of fuel rods Detection of possible anomaly in the clad / oxide layer PSI / AHL / GD43 / HOTLAB / Seite 31
32 Post Irradiation Analysis of fuel rods over-canning of fuel segments Over-canning fuel segments PSI / AHL / GD43 / HOTLAB / Seite 32
33 Radioactive material analysis Preparation of specimen for surface analyses PSI / AHL / GD43 / HOTLAB / Seite 33
34 Radioactive material analysis Optical microscopy Modification of the fuel morphology with burn-up in UO 2 (mid pellet radius, etched) 40 MWd/kgU 73 MWd/kgU PSI / AHL / GD43 / HOTLAB / Seite 34
35 Radioactive material analysis EPMA / Chemical analysis of the surface Fuel structure and composition Detailed analysis of irradiated commercial fuel (element mapping, grain subdivision and FP precipitation PSI / AHL / GD43 / HOTLAB / Seite 35
36 Radioactive material analysis EPMA / Chemical analysis of the surface Fission product distribution in irradiated fuel PSI / AHL / GD43 / HOTLAB / Seite 36
37 Radioactive material analysis EPMA / Chemical analysis of the surface U Analysis of complex material (result of a severe accident test) What you see is not always the reality O Zr PSI / AHL / GD43 / HOTLAB / Seite 37
38 Radioactive material analysis Specimen holder for XAS examination in SLS Access to more specific information XAS: x-ray absorption spectroscopy in SLS / Collaboration with LNM PSI / AHL / GD43 / HOTLAB / Seite 38
39 Radioactive material analysis Analysis of «unexpected» radioactive material Determination of the analysis method Analysis and interpretation Usually request a fast response PSI / AHL / GD43 / HOTLAB / Seite 39
40 Radioactive material analysis «Exotic» investigation of radioactive materials using synergy in PSI (Analysis of a leaker in the HOTLAB and SINQ / H distribution in clad) PSI / AHL / GD43 / HOTLAB / Seite 40
41 Radioactive material analysis Comparison local (HOTLAB) and global (SINQ) analyses Hot extraction Neutron radiography [H] / ppm Distance to fracture (mm) PSI / AHL / GD43 / HOTLAB / Seite 41
42 Radioactive material analysis Development of new analysis method Better understand and model the nuclear materials Investigation of the hydride structure in cladding (innovative visualisation without etching and investigation methods) PSI / AHL / GD43 / HOTLAB / Seite 42
43 Radioactive material analysis Research work / development of new methods SIMS - Solving isobaric interferences between Pu and Am in (Th, Pu)O 2 System of 4 equations I = I Pu + I Am I = I PuO + I AmO I I I I 239 Pu 255 PuO 243 Am 259 AmO I = I I = I 241 Pu 257 PuO 241 Am 257 AmO and 4 unknowns 241 I Pu 241 I Am 257 I PuO 257 I AmO Intensity (c/s) Th 233 U 239 Pu 238 Pu 240 Pu 232 Th 16 O 241 Am+ 241 Pu 242 Pu Am 243 Am 232 Th 18 O 255 (PuO) 254 (PuO) 256 (PuO) 257 (AmO)+ 257 (PuO) 258 (PuO)+ 258 (AmO) 259 (AmO) Mass [amu] PSI / AHL / GD43 / HOTLAB / Seite 43
44 Radioactive material analysis Research work / PhD in AHL Fundamental studies of the mass discrimination in multiple-collector inductively coupled plasma mass spectrometry Improvement of the instrumentation PSI / AHL / GD43 / HOTLAB / Seite 44
45 Radioactive material analysis LES scientists are using the hot laboratory Investigation of transport und sorption mechanisms with radiioactive tracers / elements Critical research for waste repository Diffusions measurement in glove box (LES Info) PSI / AHL / GD43 / HOTLAB / Seite 45
46 PSI / AHL / GD43 / HOTLAB / Seite 46
47 Conclusion Very good safety culture High flexibility and innovative thinking of the collaborators Standard PIE capabilities for fuel rods Good and mostly up to date analytical tools Good collaboration with the Swiss power plants / insure enough PIE work for the HOTLAB Good collaboration with research groups in PSI (LNM, LES, ) and international partners (EUprojects, EPRI, WSE, Studsvik, AREVA) PSI / AHL / GD43 / HOTLAB / Seite 47
48 Conclusion The stringent regulatory field reduce our reactivity and stresses our capacity The finance of AHL are sound but under pressure The funding needed to maintain and adapt the infrastructure to the new regulation and research demands is not insured on the long term AHL has been demonstrated its ability to conduct and perform complex projects safely and efficiently AHL has demonstrated its capacity to improve and further develop its specimen preparation and analysis methods to the interest of the Lab-users PSI / AHL / GD43 / HOTLAB / Seite 48
49 Conclusion The HOTLAB is a key facility for NES, the PSI and Switzerland We have to keep it up to date and insure the safety and needed capabilities for all its users Possible with the common financial effort from PSI, Swissnuclear, our project partners and the quality of our work PSI / AHL / GD43 / HOTLAB / Seite 49
50 Acknowledgement Thanks to the AHL crew without whom nothing would be possible and to our partners who ensure the future of the HOTLAB Seite 50
The PSI Hotlab Who we are and what we do NES Event
WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN Marco Streit :: NES / AHL The PSI Hotlab Who we are and what we do Highlights @ NES Event 24.10.2017 Facts & Figures of PSI Hotlab Built 1961 1963 (11 Mio CHF) Continuously
Wir schaffen Wissen heute für morgen Paul Scherrer Institut Recent Highlights from the Nuclear Engineering R&D at PSI
Wir schaffen Wissen heute für morgen Paul Scherrer Institut Martin A. Zimmermann Recent Highlights from the Nuclear Engineering R&D at PSI NES Strategy for PAB 28. 2. 2013 Energy Strategy 2050 In 2011,
Labor für Endlagersicherheit
WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN Sergey V. Churakov :: Laboratory for Waste Management :: Paul Scherrer Institut Labor für Endlagersicherheit NES Kompetenzen und Highlights, Oktober 18, 2016, PSI Outline
The MEGAPIE PIE sample preparation
Wir schaffen Wissen heute für morgen Technology and Components of Accelerator Driven Systems (TCADS-2) The MEGAPIE PIE sample preparation M. Wohlmuther, V. Boutellier, Y. Dai, D. Gavillet, K. Geissmann,
SPentfuel characterisation Program for the Implementation of Repositories
SPentfuel characterisation Program for the Implementation of Repositories WP2 & WP4 Development of measurement methods and techniques to characterise spent nuclear fuel Henrik Widestrand and Peter Schillebeeckx
Spent fuel inventory calculations in the SPIRE project: Current limits and expected improvements
WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN D. Rochman and M. Seidl, for the SPIRE project Spent fuel inventory calculations in the SPIRE project: Current limits and expected improvements Implementing Geological
Development of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel
Development of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel S. Caruso, A. Shama, M. M. Gutierrez National Cooperative for the Disposal of Radioactive
Polonium Behavior in eutectic Lead Bismuth Alloy
Polonium Behavior in eutectic Lead Bismuth Alloy J. Neuhausen, F. v. Rohr, S. Horn, S. Lüthi, D. Schumann Laboratory for Radio- and Environmental Chemistry Paul Scherrer Institute, CH-5232 Villigen PSI,
ESNII + WP7 Fuel Safety
ESNII + WP7 Fuel Safety Nathalie CHAUVIN CEA Cadarache Fuel Studies Department CEA/DEN/Cad ESNII + 24 MARS 2015 17-19 March, 2015 PAGE 1 WP7 Fuel Safety Fuel characteristics of 3 prototypes (starting cores)
Radioactive Waste Characterization and Management Post-Assessment Answer Key Page 1 of 7
Key Page 1 of 7 1. Uranium tailings from mining operations are typically left in piles to. a. decay b. dry c. be re-absorbed d. be shipped to a disposal site 2. is the most important radioactive component
Lesson 14: Reactivity Variations and Control
Lesson 14: Reactivity Variations and Control Reactivity Variations External, Internal Short-term Variations Reactivity Feedbacks Reactivity Coefficients and Safety Medium-term Variations Xe 135 Poisoning
Study of Burnup Reactivity and Isotopic Inventories in REBUS Program
Study of Burnup Reactivity and Isotopic Inventories in REBUS Program T. Yamamoto 1, Y. Ando 1, K. Sakurada 2, Y. Hayashi 2, and K. Azekura 3 1 Japan Nuclear Energy Safety Organization (JNES) 2 Toshiba
FIRST-Nuclides: Outcome, Open Questions and Steps Forward
FIRST-Nuclides: Outcome, Open Questions and Steps Forward IGD-TP Exchange Forum n 5, October 28-30th, 2014, Kalmar, Sweden Bernhard Kienzler, KIT-INE, Germany Institut für Nukleare Entsorgung (INE) Subatech
The outermost container into which vitrified high level waste or spent fuel rods are to be placed. Made of stainless steel or inert alloy.
Glossary of Nuclear Waste Terms Atom The basic component of all matter; it is the smallest part of an element having all the chemical properties of that element. Atoms are made up of protons and neutrons
Handling Radioactive Waste from the Proton Accelerator Facility at the Paul Scherrer Institut (PSI) - Always Surprising? 13320
Handling Radioactive Waste from the Proton Accelerator Facility at the Paul Scherrer Institut (PSI) - Always Surprising? 13320 ABSTRACT Joachim Müth, Paul Scherrer Institute, CH-5232 Villigen, Switzerland
DEVELOPMENT OF HIGH RESOLUTION X-RAY CT TECHNIQUE FOR IRRADIATED FUEL ASSEMBLY
More Info at Open Access Database www.ndt.net/?id=18598 DEVELOPMENT OF HIGH RESOLUTION X-RAY CT TECHNIQUE FOR IRRADIATED FUEL ASSEMBLY A. Ishimi, K. Katsuyama, H. Kodaka, H. Furuya Japan Atomic Energy
Utilization of Egyptian Research Reactor and modes of collaboration
Utilization of Egyptian Research Reactor and modes of collaboration Mohamed A. GAHEEN Director of ETRR-2, Egypt TM on Research Reactor Application for Materials Under High Neutron Fluence, Vienna, 17-21
Calculation of dose rate, decay heat and criticality for verifying compliance with transport limits for steel packages
2005, April 14th & 15th Radioactivity, radionuclides & radiation Lars Niemann Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Nuclear Facilities Decommissioning Division Calculation of dose rate,
Assessment of Radioactivity Inventory a key parameter in the clearance for recycling process
Assessment of Radioactivity Inventory a key parameter in the clearance for recycling process MR2014 Symposium, April 8-10, 2014, Studsvik, Nyköping, Sweden Klas Lundgren Arne Larsson Background Studsvik
English text only NUCLEAR ENERGY AGENCY NUCLEAR SCIENCE COMMITTEE
Unclassified NEA/NSC/DOC(2007)9 NEA/NSC/DOC(2007)9 Unclassified Organisation de Coopération et de Développement Economiques Organisation for Economic Co-operation and Development 14-Dec-2007 English text
NES präsentiert: Kompetenzen & Highlights
NES präsentiert: Kompetenzen & Highlights WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN Andreas Pautz, Bereichsleiter Nukleare Energie und Sicherheit (NES) :: Paul Scherrer Institut NES präsentiert: Kompetenzen
Title: Assessment of activity inventories in Swedish LWRs at time of decommissioning
Paper presented at the seminar Decommissioning of nuclear facilities, Studsvik, Nyköping, Sweden, 14-16 September 2010. Title: Assessment of activity inventories in Swedish LWRs at time of decommissioning
Nuclear Research Reactors
Nuclear Research Reactors Seminar on Nuclear Science and Technology for Diplomats P. Adelfang (+)Division of Nuclear Fuel Cycle and Waste Technology (NEFW) Dept. of Nuclear Energy (NE) IAEA, Vienna, February
Present Status of JEFF-3.1 Qualification for LWR. Reactivity and Fuel Inventory Prediction
Present Status of JEFF-3.1 Qualification for LWR Reactivity and Fuel Inventory Prediction Experimental Validation Group (CEA Cadarache/Saclay) D. BERNARD david.bernard@cea.fr A. COURCELLE arnaud.courcelle@cea.fr
Role of the Halden Reactor Project for TVEL nuclear fuels & materials development. B. Volkov IFE/HRP (Norway) Sochi, May 14-16
Role of the Halden Reactor Project for TVEL nuclear fuels & materials development B. Volkov IFE/HRP (Norway) Sochi, May 14-16 1 International OECD Halden Reactor Project foundation and history organisation
Original Paper Fission Gas Bubbles Characterisation in Irradiated UO 2 Fuel by SEM, EPMA and SIMS
Microchim Acta 155, 183 187 (2006) DOI 10.1007/s00604-006-0540-y Original Paper Fission Gas Bubbles Characterisation in Irradiated UO 2 Fuel by SEM, EPMA and SIMS Jérôme Lamontagne, Lionel Desgranges,
sustainable nuclear energy
Marcoule in service of > Atalante sustainable nuclear energy ATALANTE at the heart of international nuclear research Global energy demand will more than double in the next 40 years. Competitive, with minimal
MA/LLFP Transmutation Experiment Options in the Future Monju Core
MA/LLFP Transmutation Experiment Options in the Future Monju Core Akihiro KITANO 1, Hiroshi NISHI 1*, Junichi ISHIBASHI 1 and Mitsuaki YAMAOKA 2 1 International Cooperation and Technology Development Center,
Reduction of Radioactive Waste by Accelerators
October 9-10, 2014 International Symposium on Present Status and Future Perspective for Reducing Radioactive Waste - Aiming for Zero-Release - Reduction of Radioactive Waste by Accelerators Hiroyuki Oigawa
Monitoring of Ionizing Radiations facilities Experience and challenge
Monitoring of Ionizing Radiations facilities Experience and challenge Lebanese Atomic Energy Commission The LAEC was established in 1996 with the full support and assistance of the IAEA, having the mandate
SIMPLIFIED BENCHMARK SPECIFICATION BASED ON #2670 ISTC VVER PIE. Ludmila Markova Frantisek Havluj NRI Rez, Czech Republic ABSTRACT
12 th Meeting of AER Working Group E on 'Physical Problems of Spent Fuel, Radwaste and Nuclear Power Plants Decommissioning' Modra, Slovakia, April 16-18, 2007 SIMPLIFIED BENCHMARK SPECIFICATION BASED
Idaho National Laboratory Reactor Analysis Applications of the Serpent Lattice Physics Code
Idaho National Laboratory Reactor Analysis Applications of the Serpent Lattice Physics Code By Frederick N. Gleicher II, Javier Ortensi, Benjamin Baker, and Mark DeHart Outline Intra-Pin Power and Flux
more ?Learning about plutonium
?Learning about plutonium more What is plutonium? Plutonium (PU) is a hard white metal that looks like iron. It melts at 640 Celsius, turns into plutonium oxide when exposed to air and can catch fire.
Safety considerations for Fusion Energy: From experimental facilities to Fusion Nuclear Science and beyond
Safety considerations for Fusion Energy: From experimental facilities to Fusion Nuclear Science and beyond 1st IAEA TM on the Safety, Design and Technology of Fusion Power Plants May 3, 2016 Susana Reyes,
NEW DEVELOPMENTS OF AUTORADIOGRAPHY TECHNIQUE TO IMPROVE ALPHA AND BETA MEASUREMENTS FOR DECOMMISSIONING FACILITIES
NEW DEVELOPMENTS OF AUTORADIOGRAPHY TECHNIQUE TO IMPROVE ALPHA AND BETA MEASUREMENTS FOR DECOMMISSIONING FACILITIES PASCAL FICHET, C MOUGEL, Y DESNOYERS, P SARDINI, H WORD DEN SERVICE D ETUDES ANALYTIQUES
RECH-1 RESEARCH REACTOR: PRESENT AND FUTURE APPLICATIONS
RECH-1 RESEARCH REACTOR: PRESENT AND FUTURE APPLICATIONS E.Vargas, S. Bustamante, R. Crispieri Subdepartamento de reactores Comisión Chilena de Energía Nuclear, Amunategui 95, P.O.Box 188-D, Santiago Chile
ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS
ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS Hernán G. Meier, Martín Brizuela, Alexis R. A. Maître and Felipe Albornoz INVAP S.E. Comandante Luis Piedra Buena 4950, 8400 San Carlos
The European Commission s science and knowledge service
The European Commission s science and knowledge service Joint Research Centre EU activities in the MSR project O. Beneš JRC Karlsruhe ITU One of the 7 research institutes of the European Commission s Joint
Science and Technology. Solutions, Separation Techniques, and the PUREX Process for Reprocessing Nuclear Waste
Science and Technology Solutions, Separation Techniques, and the PUREX Process for Reprocessing Nuclear Waste Spent Fuel Rods General Accounting Office Fission products that emit beta and gamma radiation
Introduction to ESS - NIUS
Paul Scherrer Institut W. Wagner, Eberhard H. Lehmann Wir schaffen Wissen heute für morgen Introduction to ESS - NIUS PSI, 25. April 2012 OUTLINE Purpose of ESS-NIUS Situation in Neutron Imaging TODAY
IAEA-SM-367/10/04/P SCREENING AND RADIOMETRIC MEASUREMENT OF ENVIRONMENTAL SWIPE SAMPLES
IAEA-SM-367/10/04/P SCREENING AND RADIOMETRIC MEASUREMENT OF ENVIRONMENTAL SWIPE SAMPLES V. MAIOROV, A. CIURAPINSKI, W. RAAB and V. JANSTA Safeguards Analytical Laboratory, International Atomic Energy
CHAPTER 25: NUCLEAR CHEMISTRY. Mrs. Brayfield
CHAPTER 25: NUCLEAR CHEMISTRY Mrs. Brayfield CHEMICAL VS. NUCLEAR When you hear the word nuclear, what do you think of? What makes nuclear reactions different from chemical reactions? The speed of nuclear
NUCLEAR EDUCATION AND TRAINING COURSES AS A COMMERCIAL PRODUCT OF A LOW POWER RESEARCH REACTOR
NUCLEAR EDUCATION AND TRAINING COURSES AS A COMMERCIAL PRODUCT OF A LOW POWER RESEARCH REACTOR H.BÖCK, M.VILLA, G.STEINHAUSER Vienna University of Technology/Atominstitut Vienna Austria boeck@ati.ac.at
1. INTRODUCTION 2. EAEA EXISTING CAPABILITIES AND FACILITIES
EGYPT FINAL REPORT FOR THE CRP ON DEVELOPING TECHNIQUES FOR SMALL- SCALE, INDIGENOUS PRODUCTION OF MO-99 USING LOW- ENRICHED URANIUM (LEU) OR NEUTRON ACTIVATION 1. INTRODUCTION The Egypt country report
JHR PROJECT. IRRADIATION DEVICES IN-SERVICE INSPECTION OF NUCLEAR PRESSURE EQUIPMENT S.
JHR PROJECT. IRRADIATION DEVICES IN-SERVICE INSPECTION OF NUCLEAR PRESSURE EQUIPMENT S. Investigation of Non DESTRUCTIVE EXAMINATIONS For INSPECTION Purposes. S.Gaillot CEA-France IGORR 18 & IAEA Workshop
Production. David Nusbaum Project on Managing the Atom, Belfer Center October 4, 2011
Production David Nusbaum Project on Managing the Atom, Belfer Center October 4, 2011 Where are we? Nuclear Fuel Cycle Background Pu- Radioactive, chemical element, of the actinoid series of the periodic
The analysis of particles of nuclear material finding the proverbial needle in a hay stack
San Diego, 18-22 February 2010 AAAS Annual Meeting 1 The analysis of particles of nuclear material finding the proverbial needle in a hay stack AAAS Annual Meeting San Diego, February 19, 2010 Klaus Luetzenkirchen
RADIOACTIVITY. An atom consists of protons, neutrons and electrons.
RADIOACTIVITY An atom consists of protons, neutrons and electrons. - Protons and neutrons are inside the nucleus - Electrons revolve around the nucleus in specific orbits ATOMIC NUMBER: - Total number
Sampling based on Bayesian statistics and scaling factors
JRP ENV54 MetroDecom 2nd Workshop EC-JRC Directorate Nuclear Safety and Security Ispra, Italy, 11-12 October 2016 Sampling based on Bayesian statistics and scaling factors P. De Felice (1), S. Jerome (2),
Multiphysics Simulations for the design of a Superconducting magnet for proton therapy
WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN Paul Scherrer Institut Multiphysics Simulations for the design of a Superconducting magnet for proton therapy Ciro Calzolaio October 19, 2017 OUTLINE Superconducting
IdentiFINDER Digital Hand Held Spectrometer & Dose Rate Meter for Portable Applications
fire IdentiFINDER Digital Hand Held Spectrometer & The world s smallest spectrometer and dose rate meter designed for portable applications. safety security identifinder - CH (yellow) CZT and neutron detector
Chemical Separations of Pu- 238 from Irradiated Neptunium Targets
Chemical Separations of Pu- 238 from Irradiated Neptunium Targets David DePaoli, Dennis Benker, Kevin Felker Nuclear and Emerging Technologies for Space 2015 (NETS) February 23, 2015 ORNL is managed by
NDT as a tool, for Post-Irradiation Examination.
17th World Conference on Nondestructive Testing, 25-28 Oct 2008, Shanghai, China NDT as a tool, for Post-Irradiation Examination. Abdeldjalil ALGHEM, Mourad KADOUMA, Rabah BENADDAD Nuclear research center
Keywords: Safeguards, Destructive Analysis, Environmental Sampling
Activities at Forschungszentrum Jülich in Safeguards Analytical Techniques and Measurements M. Dürr a*, A. Knott b, R. Middendorp a, I. Niemeyer a, S. Küppers a, M. Zoriy a, M. Froning a, D. Bosbach a
Nuclear Data for Reactor Physics: Cross Sections and Level Densities in in the Actinide Region. J.N. Wilson Institut de Physique Nucléaire, Orsay
Nuclear Data for Reactor Physics: Cross Sections and Level Densities in in the Actinide Region J.N. Wilson Institut de Physique Nucléaire, Orsay Talk Plan Talk Plan The importance of innovative nuclear
Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB
Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB K. M. Feng (Southwestern Institute of Physics, China) Presented at 8th IAEA Technical Meeting on Fusion Power Plant Safety
ASSESSMENT OF THE EQUILIBRIUM STATE IN REACTOR-BASED PLUTONIUM OR TRANSURANICS MULTI-RECYCLING
ASSESSMENT OF THE EQUILIBRIUM STATE IN REACTOR-BASED PLUTONIUM OR TRANSURANICS MULTI-RECYCLING T.K. Kim, T.A. Taiwo, J.A. Stillman, R.N. Hill and P.J. Finck Argonne National Laboratory, U.S. Abstract An
Review of the primary coolant chemistry at NPP Temelín and its impact on the fuel cladding
Review of the primary coolant chemistry at NPP Temelín and its impact on the fuel cladding M. Mikloš, K. Vonková, J. Kysela Research Centre Řez Ltd, 250 68 Řež, Czech Republic D. Ernst NPP Temelín, Reactor
Nuclear Fission. Conceptual Physics 11 th Edition. Nuclear Fission. Nuclear Fission. Nuclear Fission. This lecture will help you understand:
Conceptual Physics 11 th Edition A typical uranium fission reaction: Chapter 34: NUCLEAR FISSION AND FUSION Note the mass number as well as atomic numbers balance. This lecture will help you understand:
AN OVERVIEW OF NUCLEAR ENERGY. Prof. Mushtaq Ahmad, MS, PhD, MIT, USA
AN OVERVIEW OF NUCLEAR ENERGY Prof. Mushtaq Ahmad, MS, PhD, MIT, USA Outline of the Seminar 2 Motivation and Importance of Nuclear Energy Future Energy Planning in the Kingdom Current Status of Nuclear
The Swedish National Geodata Strategy and the Geodata Project
The Swedish National Geodata Strategy and the Geodata Project Ewa Rannestig, Head of NSDI Co-ordination Unit, Lantmäteriet, ewa.rannstig@lm.se Ulf Sandgren, Project Manager Geodata Project, Lantmäteriet,
The Use of Self-Induced XRF to Quantify the Pu Content in PWR Spent Nuclear Fuel
The Use of Self-Induced XRF to Quantify the Pu Content in PWR Spent Nuclear Fuel William S. Charlton, Daniel Strohmeyer, Alissa Stafford Texas A&M University, College Station, TX 77843-3133 USA Steve Saavedra
Radioactive Inventory at the Fukushima NPP
Radioactive Inventory at the Fukushima NPP G. Pretzsch, V. Hannstein, M. Wehrfritz (GRS) Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbh Schwertnergasse 1, 50667 Köln, Germany Abstract: The paper
The Effect of Burnup on Reactivity for VVER-1000 with MOXGD and UGD Fuel Assemblies Using MCNPX Code
Journal of Nuclear and Particle Physics 2016, 6(3): 61-71 DOI: 10.5923/j.jnpp.20160603.03 The Effect of Burnup on Reactivity for VVER-1000 with MOXGD and UGD Fuel Assemblies Using MCNPX Code Heba K. Louis
Development of education and training programs using ISIS research reactor
Development of education and training programs using ISIS research reactor F. Foulon 1, B. Lescop 1, X. Wohleber 2 1) National Institute for Nuclear Science and Technology, CEA-Saclay,France 2) Nuclear
ITER Participation and Possible Fusion Energy Development Path of Korea
1 ITER Participation and Possible Fusion Energy Development Path of Korea C. S. Kim, S. Cho, D. I. Choi ITER Korea TFT, 52 Eoeun-dong, Yuseong-gu, Daejeon 305-333, Korea kimkim@kbsi.re.kr The objective
POLICY ISSUE (INFORMATION)
POLICY ISSUE (INFORMATION) August 12, 2011 SECY-11-0112 FOR: FROM: SUBJECT: The Commissioners Michael R. Johnson, Director /RA/ Office of New Reactors STAFF ASSESSMENT OF SELECTED SMALL MODULAR REACTOR
11. Radioactive Waste Management AP1000 Design Control Document
CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated
RADIOLOGICAL CHARACTERIZATION Laboratory Procedures
RADIOLOGICAL CHARACTERIZATION Laboratory Procedures LORNA JEAN H. PALAD Health Physics Research Unit Philippine Nuclear Research Institute Commonwealth Avenue, Quezon city Philippines 3-7 December 2007
EXPERIENCE OF TEST OPERATION FOR REMOVAL OF FISSION PRODUCT NUCLIDES IN TRU-LIQUID WASTE AND CONCENTRATED NITRIC ACID USING INORGANIC ION EXCHANGERS
EXPERIENCE OF TEST OPERATION FOR REMOVAL OF FISSION PRODUCT NUCLIDES IN TRU-LIQUID WASTE AND CONCENTRATED NITRIC ACID USING INORGANIC ION EXCHANGERS ABSTRACT H. Tajiri, T. Mimori, K. Miyajima, T. Uchikoshi
Ultratrace analysis of radionuclides by AMS
Ultratrace analysis of radionuclides by AMS Francesca Quinto Contact information: francesca.quinto@kit.edu Karlsruhe Institute of Technology, Please insert a figure in the master transparency. KIT University
QUADRATIC DEPLETION MODEL FOR GADOLINIUM ISOTOPES IN CASMO-5
Advances in Nuclear Fuel Management IV (ANFM 2009) Hilton Head Island, South Carolina, USA, April 12-15, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) QUADRATIC DEPLETION MODEL FOR
RADIOACTIVE WASTE CHARACTERIZATION IN BELGIUM. Tractebel Ariane Avenue, 7 B-1200, Brussels, Belgium ABSTRACT
RADIOACTIVE WASTE CHARACTERIZATION IN BELGIUM Serge Vanderperre, Christine Vanhaeverbeek, Koen Mannaerts, Baudouin Centner, Philippe Beguin and Michel Detilleux Tractebel Ariane Avenue, 7 B-1200, Brussels,
Decay heat calculations. A study of their validation and accuracy.
Decay heat calculations A study of their validation and accuracy. Presented by : Dr. Robert W. Mills, UK National Nuclear Laboratory. Date: 01/10/09 The UK National Nuclear Laboratory The NNL (www.nnl.co.uk)
Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source
Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source E. Hoffman, W. Stacey, G. Kessler, D. Ulevich, J. Mandrekas, A. Mauer, C. Kirby, D. Stopp, J. Noble
Microscopy AND Microanalysis MICROSCOPY SOCIETY OF AMERICA 2007
Microsc. Microanal. 13, 150 155, 2007 DOI: 10.1017/S143192760707033X Microscopy AND Microanalysis MICROSCOPY SOCIETY OF AMERICA 2007 Microbeam Analysis of Irradiated Materials: Practical Aspects Jérôme
THE INTEGRATION OF FAST REACTOR TO THE FUEL CYCLE IN SLOVAKIA
THE INTEGRATION OF FAST REACTOR TO THE FUEL CYCLE IN SLOVAKIA Radoslav ZAJAC, Petr DARILEK VUJE, Inc. Okruzna 5, SK-91864 Trnava, Slovakia Tel: +421 33 599 1316, Fax: +421 33 599 1191, Email: zajacr@vuje.sk,
2 Energy from the Nucleus
CHAPTER 4 2 Energy from the Nucleus SECTION Atomic Energy BEFORE YOU READ After you read this section, you should be able to answer these questions: What is nuclear fission? What is nuclear fusion? What
Design of the testing set-up for a nuclear fuel rod by neutron radiography at CARR
Available online at www.sciencedirect.com Physics Procedia 43 (2013 ) 307 313 The 7 th International Topical Meeting on Neutron Radiography Design of the testing set-up for a nuclear fuel rod by neutron
(1) SCK CEN, Boeretang 200, B-2400 Mol, Belgium (2) Belgonucléaire, Av. Arianelaan 4, B-1200 Brussels, Belgium
The REBUS Experimental Programme for Burn-up Credit Peter Baeten (1)*, Pierre D'hondt (1), Leo Sannen (1), Daniel Marloye (2), Benoit Lance (2), Alfred Renard (2), Jacques Basselier (2) (1) SCK CEN, Boeretang
IMPACT OF THE FISSION YIELD COVARIANCE DATA IN BURN-UP CALCULATIONS
IMPACT OF THE FISSION YIELD COVARIANCE DATA IN BRN-P CALCLATIONS O. Cabellos, D. Piedra, Carlos J. Diez Department of Nuclear Engineering, niversidad Politécnica de Madrid, Spain E-mail: oscar.cabellos@upm.es
Seaborg s Plutonium?
Seaborg s Plutonium? Eric B. Norman, Keenan J. Thomas, Kristina E. Telhami* Department of Nuclear Engineering University of California Berkeley, CA 94720 Abstract Passive x-ray and gamma ray analysis was
Determination of plutonium isotopes in spent nuclear fuel using thermal ionization mass spectrometry (TI-MS) and alpha spectrometry
Determination of plutonium isotopes in spent nuclear fuel using thermal ionization mass spectrometry (TI-MS) and alpha spectrometry Petre M.G., Mincu M., Lazăr C., Androne G., Benga A. HOTLAB 2016, October
Radiochemistry in reactor
Radiochemistry in reactor Readings: Radiochemistry in Light Water Reactors, Chapter 3 Speciation in irradiated fuel Utilization of resulting isotopics Fission Product Chemistry Fuel confined in reactor
Neutron Imaging at Spallation Neutron Sources
Neutron Imaging at Spallation Neutron Sources E.H. LEHMANN, A. KAESTNER Paul Scherrer Institut, Deptm. Spallation Neutron Source, Switzerland OUTLINE 1. Introduction: Motivation for Neutron Imaging 2.
PWR AND WWER MOX BENCHMARK CALCULATION BY HELIOS
PWR AND WWER MOX BENCHMARK CALCULATION BY HELIOS Radoslav ZAJAC 1,2), Petr DARILEK 1), Vladimir NECAS 2) 1 VUJE, Inc., Okruzna 5, 918 64 Trnava, Slovakia; zajacr@vuje.sk, darilek@vuje.sk 2 Slovak University
Fundamentals of Nuclear Power. Original slides provided by Dr. Daniel Holland
Fundamentals of Nuclear Power Original slides provided by Dr. Daniel Holland Nuclear Fission We convert mass into energy by breaking large atoms (usually Uranium) into smaller atoms. Note the increases
Chem 481 Lecture Material 4/22/09
Chem 481 Lecture Material 4/22/09 Nuclear Reactors Poisons The neutron population in an operating reactor is controlled by the use of poisons in the form of control rods. A poison is any substance that
Question to the class: What are the pros, cons, and uncertainties of using nuclear power?
Energy and Society Week 11 Section Handout Section Outline: 1. Rough sketch of nuclear power (15 minutes) 2. Radioactive decay (10 minutes) 3. Nuclear practice problems or a discussion of the appropriate
Research Article Calculations for a BWR Lattice with Adjacent Gadolinium Pins Using the Monte Carlo Cell Code Serpent v.1.1.7
Science and Technology of Nuclear Installations Volume 2, Article ID 65946, 4 pages doi:.55/2/65946 Research Article Calculations for a BWR Lattice with Adjacent Gadolinium Pins Using the Monte Carlo Cell
AP1000 European 11. Radioactive Waste Management Design Control Document
CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated
State of the Art for Fuel-Coolant Interactions Research for LFRs. Teodora Retegan, Christian Ekberg, Gunnar Skarnemark
State of the Art for Fuel-Coolant Interactions Research for LFRs Teodora Retegan, Christian Ekberg, Gunnar Skarnemark tretgan@chalmers.se Outline Chalmers Lead Cooled (Fast) Reactors Physical bariers and
Comparison of U-Pu and Th-U cycles in MSR
WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN Jiri Krepel :: Advanced Nuclear System Group :: Paul Scherrer Institut Comparison of U-Pu and Th-U cycles in MSR ThEC 2018 conference 29-31. October 2018, Brussels,
Application of national regulations for metallic materials recycling from the decommissioning of an Italian nuclear facility.
Application of national regulations for metallic materials recycling from the decommissioning of an Italian nuclear facility. Giovanni Varasano *, Leonardo Baldassarre*, Edoardo Petagna*. SOGIN Spa, ITREC
Lecture 14, 8/9/2017. Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion
Lecture 14, 8/9/2017 Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion Nuclear Reactions and the Transmutation of Elements A nuclear reaction takes place
Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations
Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations Gunter Pretzsch Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbh Radiation and Environmental Protection Division
Atomic Structure and Radioactivity
Atomic Structure and Radioactivity Models of the atom know: Plum pudding model of the atom and Rutherford and Marsden s alpha experiments, being able to explain why the evidence from the scattering experiment
Background Tritium in Environmental Water Samples. Paul Snead NCHPS Fall Meeting November 2, 2006
Background Tritium in Environmental Water Samples Paul Snead NCHPS Fall Meeting November 2, 2006 Tritium Basics Tritium ( 3 H) is a radioactive isotope of hydrogen Nucleus has one proton and two neutrons
Fuel BurnupCalculations and Uncertainties
Fuel BurnupCalculations and Uncertainties Outline Review lattice physics methods Different approaches to burnup predictions Linkage to fuel safety criteria Sources of uncertainty Survey of available codes
Radioactive effluent releases from Rokkasho Reprocessing Plant (1) - Gaseous effluent -
Radioactive effluent releases from Rokkasho Reprocessing Plant (1) - Gaseous effluent - K.Anzai, S.Keta, M.Kano *, N.Ishihara, T.Moriyama, Y.Okamura K.Ogaki, K.Noda a a Reprocessing Business Division,