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Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Status of Radioactivity Control, Status of Radioactivity Control, Safety and Risk.

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Presentation on theme: "Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Status of Radioactivity Control, Status of Radioactivity Control, Safety and Risk."— Presentation transcript:

1 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Status of Radioactivity Control, Status of Radioactivity Control, Safety and Risk Studies within WP5 P.G. Thirolf, LMU München P.G. Thirolf, LMU München Subtask B of WP5: First years’ activities: - study of containment of volatile radioactivity LMU Munich: PT, J. Neumayr, R. Stoepler, T. Deuschle - model creation and validation for activity in the ground water; oxidation of target materials FZ Jülich: R. Moormann, K. Bongardt, M. Herbst, B. Heuel-Fabianek, K. Kühn, R. Nabbi - creation of a software platform for exposure evaluations NIPNE (Bucharest): B. Vamanu, D. Vamanu, V. Acasandrei

2 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Containment of Volatile Radioactivity Xenon Iodine Krypton Bromium Freezeout at cryotrap: - 10 14 fiss./sec = 3.7. 10 14 Bq (10 kCi) (non-ionized) - Localize volatile activity on cryotrap - Mostly short-lived: decay to non-volatile species Isotope distribution from 235 U(n th,f):

3 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Cryo-Trap Prototype: - material: Al 6061 T6 (cryogenic specification) - manufacturing by thermal shrinking: heat outside tube (ca. 100 o C), cool inside tube (lN 2 ) Design: - double-walled tube - gap: 3 mm, wall thickness: 2mm - length: 1m, outside diameter 169 mm - spiral structure for mech. stability - T in = 10 K, T out = 18 K - in final operation: 1 passive heat shield - cooling power required: ca. 500 W

4 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Cryo-Trap Tests Testbench facility at MLL (Garching): - cryopanel prototype coupled to Helium refrigerator - first cooling tests with cryopanel successful Planned next actions: - measurement of temperature distribution pumping capacity isotopic retainment factors localization capability in case of vacuum leak, condensate build-up during longterm operation performance in presence of hot fission source lHe refrigerator:

5 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Exposure Evaluation: Transfer experience from nuclear reactors EURISOL radioactive inventory will come close to that of a research reactor

6 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 SEEN FROM OUTSIDE: (Regulatory bodies) SEEN FROM INSIDE: (accelerator community) QUANTITATIVE EVALUATION OF MAJOR SAFETY & RADIOPROTECTION ISSUES INCLUDING: HANDLING AND DISPOSAL OF RIB TARGETS CONTAINMENT FAILURE, ACTIVITY MIGRATION, … SPECIFIC RADIOACTIVE INVENTORIES NIPNE-contribution (Bucharest) THE HEALTH –, OCCUPATIONAL-, PUBLIC - AND ENVIRONMENTAL IMPACT OF THE EURISOL FACILITY RIB RADIOACTIVE INVENTORIES ACTIVATION PRODUCTS FISSION PRODUCTS ACTINIDES WASTE MANAGEMENT RIB FACILITY SOURCE TERMS OF ENVIRONMENTAL RELEASES LOCALIZED RADIOACTIVITY MIGRATIONAL RADIOACTIVITY (GASES, AEROSOLS, LIQUIDS) EXPOSURE PATHS & SCENARIOS, RADIOLOGICAL ASSESSMENT EXPECTED DOSES TO WORKERS AND PUBLIC, IN TYPICAL SCENARIOS DERIVED RELEASE LIMITS FOR NORMAL OPERATIONS DERIVED INTERVENTION LEVELS FOR ABNORMAL OCCURRENCES LEGAL ISSUES (Packaging the above) ENVIRONMENTAL STATEMENT: PREREQUISITE OF AUTHORIZATION DECOMMISSIONING STATEMENT: PREREQUISITE OF AUTHORIZATION RADIOLOGICAL MONITORING OF ROUTINE OPERATIONS EMERGENCY PLANNING AND PREPAREDNESS CONTINGENCY PLANS PROCEDURES OVERALL RESPONSE MANUAL Software Platform for Exposure Evaluation

7 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 WHY is it needed ? - Siting decisions - Authorization: Environmental Statement, Decommissioning Statement - Occupational monitoring - Waste management - Emergency planning - Decommissioning -> Tool needed for assessment of exposure risks Queries to address: - How radio-toxic are our isotopes ? - How risky is it to handle this piece ? - How are we likely to impact the environment, the population ? - To what extent does the law allow us to impact environment and population ? - What procedures are to be adopted in case of an accident ? - Where are we standing regarding the regulatory dose limits, in comparison with other nuclear facilities?

8 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 - A vademecum of radiological assessment data and knowledge: E-BOOK and library user interfaces - Occupational exposure: point sources - Environmental exposures: dose-to-source term correlations; critical group exposures via complex pathways, including air, water and food chain. What is the radioprotection toolkit software ? -> compilation of existing (reliable) information: Sources: IAEA, NRC (US), …

9 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 DESKTOP ASSISTANT Point Source Exposure Acute Exposure to Environmental Releases Prolonged Exposure to Environmental Releases E-BOOK SAFETY AND RADIOPROTECTION TOOLKIT Further steps: Derived Release Limits (DRL) Derived Intervention Levels (DIL) Assessment of exposure from underground water contamination Development of a resident GIS platform Cadastral Impact Analysis (GIS based) … DATA Libraries - Methodology validated, recommended and accepted by international regulatory bodies. Tools, data and knowledge to be used in environmental and health impact. modules:

10 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Example: Point Source Exposure Shielded/not shielded point-source exposure from pure- or isotopically-mixed open sources. Output: Dose-to-distance relationship. SOURCE: Oak Ridge National Laboratories. The CONDOS code. U.S. Nuclear Regulatory Commission, International RTM-95 Response Technical Manual Isotope / Mix Shielding ECF DCF Lead Iron Aluminium Water Air Concrete Exposure / Dose to distance Exposure EDE BDE

11 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Main goal is the development of a code system for calculation of the ground- water contamination at the EURISOL fence (tap water quality is required there). By preliminary activation calculations the most relevant nuclides were identified: r s = retention by sorption on soil (chromatography effect) NuclideH-3Be- 7 Na-22P-32Cl-36Fe-55Co-60Eu-152 (CERN) t 1/2 12.3 y 53 d2.6 y14.3 d 3.1E5 y 2.6 y5.3 y13.3 y rsrs < 10>10 0 < 1010- 100 < 10> 100 Yield fast n +++(+)- + Yield thermal n (-) --(+)+(-)(+)(-) Radio- toxicity (-)(+) + + The influence of the proton energy (1 or 2 GeV options in discussion for EURISOL) on the relative activation level in soil was studied: There is no significant difference between 1 an 2 GeV. Preliminary activity transport calculations were started with the FZJ code TRACE/PARTRACE on example of the Jülich site. The total activity in soil behind a 0.6 m concrete shielding was calculated to < 10 Bq/g for 30 y irradiation with a beam loss of 1 W/m from accelerator. Forschungszentrum Jülich in der Helmholtz-Gemeinschaft Activation of soil/ground water, migration of activity with ground water FZ Jülich contribution

12 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Work planned for 2006 Development of a suitable fast code for activation calculations of soil/groundwater. Completion of a compilation of k D (sorption) values for EURISOL relevant nuclides in different types of soil. Coupling of the activation code with TRACE/PARTRACE (code for transport calculations of nuclides in groundwater). Test of the combined code on the Jülich ground water test area (PEGASE). Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

13 Peter Thirolf, WP5/Subtask B EURISOL-DS Town-Meeting, Caen, 28.-30.11.05 Relevant in EURISOL for 2 reasons: a. Mobilization of activity enclosed in the oxidizing target materials (accidents with ingress of air or steam). b. Heat generation by oxidation may enhance the vaporization of mercury: Fire in the target area was found by PRA to be the most relevant driving force for activity release in SNS and ESS accidents. A compilation of oxidation rates data was generated: Next steps (2006) The data compilation will be completed. Lack of relevant data will be identified. Oxidation of target materials Forschungszentrum Jülich in der Helmholtz-Gemeinschaft


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