RESULTS FROM THE APPLICATION OF UNCERTAINTY METHODS IN THE UMS AND IN BEMUSE
|
|
- Ilene Collins
- 6 years ago
- Views:
Transcription
1 RESULTS FROM THE APPLICATION OF UNCERTAINTY METHODS IN THE UMS AND IN BEMUSE A. Petruzzi (UNIPI) Presenteb by M. Adorni (UNIPI) Kick off meeting on Uncertainty Analyses for Criticality Safety Assessment IRSN, Fontenay-aux-Roses (France) 5-6 December 2007
2 The UMS Summary of the Uncertainty Methods in UMS AEAT, UMAE, GRS & IPSN, ENUSA Comparison between Uncertainty Methods UMS Applications The BEMUSE Programme Phase II Phase III CONTENTS Conclusions 2/61
3 THE UMS The Uncertainty Methods Study (UMS) Group, following a mandate from CSNI, has compared five methods (AEAW, GRS, UMAE, IPSN, ENUSA) for calculating the uncertainty in the predictions of advanced best estimate thermalhydraulic codes OBJECTIVES 1. To gain insights into differences between features of the methods by: - comparing the different methods, step by step, when applied to the same problem; - comparing the uncertainties predicted for specified output quantities of interest; - comparing the uncertainties predicted with measured values; - drowning conclusions about the suitability of method. 2. To inform those who will take decisions on conducting uncertainty analyses, for example in the licensing requirements. 3/61
4 THE UMS A Small Break LOCA (SBLOCA) experiment performed in the Japanese facility LSTF was selected as objective of the analysis of the international UMS Group 4/61
5 Five Methods compared: THE UMS Pisa Method (UMAE): extrapolation from integral experiments; GRS, IPSN, ENUSA methods: identify and combine input uncertainties, using subjective Probability Distribution Function (pdf); AEAT method: performs a bounding analysis 5/61
6 SUMMARY OF UNCERTAINTY METHODS IN UMS AEAT METHOD The uncertainty statements must be in the form of reasonable uncertainty ranges. This is defined as the smallest range of values that includes all values for which there is reasonable certainty that they are consistent with the all available evidence. Emphasis is given to the use of experimental data independent from those used by code developers to derive suitable uncertainty values. 6/61
7 SUMMARY OF UNCERTAINTY METHODS IN UMS UMAE METHOD The basic idea is to use the accuracy gathered from the comparison between measured and calculated time trends. These must be related to qualified ITF. No need to select input uncertainties or ranges. Emphasis is given to the calculation qualification process (quality of experimental data, of dalization, of code results checked). Qualitative and quantitative criteria have been proposed to accept suitable calculation results. Fulfilments of various conditions are needed to use the method. 7/61
8 SUMMARY OF UNCERTAINTY METHODS IN UMS UMAE METHOD General Qualification Process b Code a i j Plant dalization Plant calculation GI Generic experimental data Stop of the process NO h Nodalization and user qualification FG FG g NO ITF Nodalizations Specific experimental data ITF Calculation c e d k Demonstration of Similarity ( ) (Phemena Analysis) (Scaling Laws) YES Accuracy Quantification ( ) Accuracy Extrapolation ( ) f l m ASM Calculation LN ( ) ( ) Special methodology developed Uncertainty n 8/61
9 SUMMARY OF UNCERTAINTY METHODS IN UMS GRS & IPSN METHODS The amount and the type of selected uncertain input parameters distinguishes the two methods. The methods have the capability to consider the effects of code models, BIC, solution algorithms, etc., upon calculation results (all input parameters potentially affecting uncertainties). Well established concepts from probability calculus and statistics are used. The selection of an ITF experiment makes it possible to take decisions on dominant phemena. A random value for each uncertain parameter is selected according to the specified subjective probability distribution. Use of the Wilks formula for the minimum number of code calculations. Sensitivity measures are derived. 9/61
10 SUMMARY OF UNCERTAINTY METHODS IN UMS This is based upon CSAU. ENUSA METHOD The PIRT (Phemena Identification and Ranking Table) process is used to select a reasonable number of input uncertain parameters: same objective as for the AEAT method. The ranges of variations are fixed adopting a similar approach as the AEAT method. In order to minimize the number of calculation runs, the process of combination of input uncertainties is basically the same as adopted by GRS and IPSN. This makes the difference between ENUSA and CSAU. 10/61
11 COMPARISON BETWEEN UNCERTAINTY METHODS SIMILARITY AMONG THE METHODS 1) All methods have the capability to calculate the error ranges as a function of time (continuous uncertainty bands). 2) Each method consists of a limited number of main steps and a larger number of sub-steps that appear from the method use. 3) Each method requires resources of man-years to be used by a competent technician on the first time (status 1998). 4) Some features of each method may be connected with the features of the adopted code. 5) Each method requires the selection of a code and of a transient scenario. 6) Each method makes use of experimental data, to a different extent and at different levels. 7) Each method needs a qualified code. 8) Each method aims at providing information useful to a decisionmaker. 11/61
12 COMPARISON BETWEEN UNCERTAINTY METHODS MAIN CHARACTERISTICS OF CONSIDERED UNCERTAINTY METHODS GENERAL CHARACTERISTICS AEAT CSAU GRS UMAE 1 2 Restriction on the number of input uncertain parameters Deriving input uncertainty ranges n.a. 3 4 Assigning subjective probability distributions Use of statistics (a) 5 6 Use of response surface technique Necessity of specific data for scaling (b) 7 Quantification of code calculation accuracy 8 Use of expert groups 9 Use of biases on output (a) : To a limited extent. (b) : At a qualitative level, during code validation. 12/61
13 COMPARISON BETWEEN UNCERTAINTY METHODS COMPARISON AMONG RELEVANT FEATURES FEATURE Determination of uncertain parameters and of input uncertainty ranges Selection of uncertain parameter values within the determined range for code calculations Support of identification and ranking of main parameter and modelling uncertainties Account for state of kwledge of uncertain parameters (distribution of input uncertainties) Probabilistic uncertainty statement Statistical rigour Kwledge of code specifics may reduce resources necessary to the analysis Number of code runs independent from number of input and output parameters Quantitative information about influence of a limited number of code runs Continuous-valued output parameters Sensitivity measures of input parameters on output parameters AEAT experts experts n.a. CSAU experts experts GRS experts random selection UMAE (1) t necessary (1) Differences between experimental and used input data. 13/61
14 COMPARISON BETWEEN UNCERTAINTY METHODS 14/61
15 COMPARISON BETWEEN UNCERTAINTY METHODS 15/61
16 COMPARISON BETWEEN UNCERTAINTY METHODS 16/61
17 COMPARISON BETWEEN UNCERTAINTY METHODS 17/61
18 COMPARISON BETWEEN UNCERTAINTY METHODS 18/61
19 COMPARISON BETWEEN UNCERTAINTY METHODS 19/61
20 COMPARISON BETWEEN UNCERTAINTY METHODS 20/61
21 UMS APPLICATION UNCERTAINTY IN UP PRESSURE PREDICTED BY THE VARIOUS METHODS 21/61
22 UMS APPLICATION UNCERTAINTY IN MASS INVENTORY PREDICTED BY THE VARIOUS METHODS 22/61
23 UMS APPLICATION UNCERTAINTY IN ROD SURFACE TEMPERATURE PREDICTED BY THE VARIOUS METHODS 23/61
24 UMS APPLICATION AMPLITUDE OF UNCERTAINTY BANDS FOR PRESSURE 24/61
25 UMS APPLICATION AMPLITUDE OF UNCERTAINTY BANDS FOR ROD SURFACE TEMPERATURE 25/61
26 OECD BEMUSE BEMUSE PROGRAMME Objectives Description of the Work LOFT Facility and Test L2-5 PARTICIPANTS RESULTS (PHASE II) Nodalization Qualification Qualitative Accuracy Evaluation Quantitative Accuracy Evaluation Sensitivity Study PARTICIPANTS RESULTS (PHASE III) 26/61
27 BEMUSE: Objectives The BEMUSE Programme has been promoted by the Working Group on Accident Management and Analysis (GAMA) and endorsed by the Committee on the Safety of Nuclear Installations (CSNI) The Objectives of the activity are: To Evaluate the Practicability, the Quality and the Reliability of Best-Estimate (BE) Methods Including Uncertainty Evaluation in Applications Relevant to Nuclear Reactor Safety To Develop Common Understanding To Promote/Facilitate their use by the Regulatory Bodies and the Industry 27/61
28 BEMUSE: Description of the Work STEP 1: (NEA/SEN/SIN/AMA(2003)8) Phase I: (March 2003 March 2004) Presentation in advance of the uncertainty evaluation methodology to be used by participants Phase II: (September 2003 December 2004) Re-analysis of the ISP-13 exercise, post-test analysis of the LOFT L2-5 test calculation Phase III: (December 2004 April 2006) Uncertainty evaluation of the L2-5 test calculations, and deduced first conclusions on the methods and suggestions for improvement 28/61
29 BEMUSE: Description of the Work STEP 2: (NEA/SEN/SIN/AMA(2003)8) Phase IV: (October 2005 October 2007) Phase V: Best-estimate analysis of the LBLOCA in NPP Sensitivity studies and uncertainty evaluation for the NPP-LB (with and without methodology improvements resulting from Phase III) Phase VI: Status report on the area, classification of the methods, conclusions and recommendations 29/61
30 BEMUSE: Participating Organizations 14 Participating Organizations; 7 TH System Codes; 8 Uncertainty Methodologies 30/61
31 BEMUSE: LOFT Facility 50-MWt PWR with instrumentation to measure and provide data on the TH and nuclear conditions Operation of the LOFT system is typical of large (~1000 MWe) commercial PWR operations. LOFT facility consists of: RPV (core with 1300 unpressurized nuclear FR m) Intact Loop (SG, PRZ and 2 primary CPs connected in parallel) Broken Loop with a simulated pump, simulated SG, 2 break plane orifices, 2 QOBV and 2 isolation valves; A blowdown suppression system consisting of a header, suppression tank and a spray system An ECC injection system consisting of two LPIS pumps, HPIS pumps and two accumulators 31/61
32 BEMUSE: LOFT Facility 32/61
33 BEMUSE: TEST L2-5 DOUBLED-ENDED 200 % COLD LEG BREAK 33/61
34 PARTICIPANTS RESULTS (PHASE II) A CONSISTENT CODE QUALIFICATION PROCESS BASED ON UMAE CRITERIA HAS BEEN APPLIED TO PHASE 2 OF BEMUSE NODALIZATION QUALIFICATION Nodalization Tables Pressures Vs Length Curve QUALITATIVE ACCURACY EVALUATION Resulting Time Sequence of Events Relevant Thermalhydraulic Aspects (RTA) Experimental Time Trends Comparisons Qualitative Judgments QUANTITATIVE ACCURACY EVALUATION Application of the FFTBM 34/61
35 PARTICIPANTS RESULTS (PHASE II) Code Resources 14 Participating Organizations; 7 TH System Codes 35/61
36 PARTICIPANTS RESULTS (PHASE II) NODALIZATION QUALIFICATION Part A Part B 36/61
37 PARTICIPANTS RESULTS (PHASE II) NODALIZATION QUALIFICATION Part A: Nodalization Development 37/61
38 PARTICIPANTS RESULTS (PHASE II) Part B: Steady State Level 38/61
39 PARTICIPANTS RESULTS (PHASE II) Results of the Nodalization Qualification QA and QB should be less than 1. 39/61
40 PARTICIPANTS RESULTS (PHASE II) Results of the Nodalization Qualification Qa Qb CEA [C25] IRSN [C25] NRI-2 [A20] GRS [A12] KFKI [A20] UPI [R5] NRI-1 [R5] UPC [R5] KINS [R5] TAEK [R5] PSI [TR4] EDO [T97] JNES [TM55] KAERI [M23] Global Acceptability Factors Organization's Name 40/61
41 PARTICIPANTS RESULTS (PHASE II) Pressures Length Curve CEA [C25] ( MPa) EDOGIDRO [T97] ( MPa) GRS [A12] ( MPa) IRSN [C25] ( MPa) JNES [TM55] ( MPa) KAERI [M23] ( MPa) KFKI [A20] ( MPa) KINS [R5] ( MPa) NRI-1 [R5] ( MPa) NRI-2 [A20] ( MPa) PSI [TR4] ( MPa) TAEK [R5] ( MPa) UPC [R5] ( MPa) UPI [R5] ( MPa) Experimental Normalized Pressure (-) HL IN HL OUT UT TOP SG OUT LOOP SEAL PUMP OUT CL IN CL OUT LP BAF TAF HL IN SG IN OUT SG NOZZLE PUMP IN Loop Length (m) 41/61
42 PARTICIPANTS RESULTS (PHASE II) QUALITATIVE ACCURACY EVALUATION Resulting Time sequence of Events Time After Experiment Initiation (s) Maximum cladding temperature reached Accumulator emptied LPIS injection terminated CEA [C25] EDOGIDRO [T97] GRS [A12] IRSN [C25] JNES [TM55] KAERI [M23] KFKI [A20] KINS [R5] NRI-1 [R5] NRI-2 [A20] PSI [TR4] TAEK [R5] UPC [R5] UPI [R5] Experimental Time (s) Core cladding fully quenched 42/61
43 PARTICIPANTS RESULTS (PHASE II) Experimental Time Trends Comparisons Qualitative Judgments Pressure (MPa) CEA [C25] EDOGIDRO [T97] GRS [A12] IRSN [C25] JNES [TM55] KAERI [M23] KFKI [A20] KINS [R5] NRI-1 [R5] NRI-2 [A20] PSI [TR4] TAEK [R5] UPC [R5] UPI [R5] EXP: PE-PC-002 Time (s) 43/61
44 PARTICIPANTS RESULTS (PHASE II) Core Geometry and Position for the Hot Rod Cladding Temperatures ZONE 4 = HOT ROD (RODS N = 1) ZONE 3 = HOT CHANNEL (RODS N = 203) ZONE 2 = AVERAGE CHANNEL (RODS N = 876) ZONE 1 = PERIPHERAL CHANNEL (RODS N = 220) CONTROL RODS (RODS N = 137) TAF TOP 1.0 m 2/3 ZONE m 0.4 m BOTTOM BAF ZONE 4: HOT ROD (FUEL ASSEMBLY N 5) - HEIGHT: 2/ J N A B C D E F G H I J K L M N O PCT Min : 5H (0.94 m K) 8 9 PCT MAX = PCT Ref : 5H (0.61 m K) /61
45 PARTICIPANTS RESULTS (PHASE II) Experimental Time Trends Comparisons Qualitative Judgments Temperature (K) CEA [C25] GRS [A12] JNES [TM55] KFKI [A20] NRI-1 [R5] PSI [TR4] UPC [R5] PCTmax: TE-5H EDOGIDRO [T97] IRSN [C25] KAERI [M23] KINS [R5] NRI-2 [A20] TAEK [R5] UPI [R5] PCTmin: TE-5H Time (s) 45/61
46 PARTICIPANTS RESULTS (PHASE II) QUANTITATIVE ACCURACY EVALUATION (AA) tot (AA)p1 (AA)tot 0.35 AA P-1 & AA TOT (AA) p CEA [C25] IRSN [C25] NRI-2 [A20] GRS [A12] KFKI [A20] UPI [R5] NRI-1 [R5] UPC [R5] KINS [R5] Organization's Name TAEK [R5] PSI [TR4] EDO [T97] JNES [TM55] KAERI [M23] 46/61
47 PARTICIPANTS RESULTS (PHASE II) USER S EFFECT ON BEMUSE User effect (UE) is a source of uncertainty (it might result in the largest contribution to the uncertainty) User expertise, Quality and comprehensiveness of the code-user manual Database available for performing the analysis UE is originated by: A) Nodalization development QA; B) Interpreting the supplied (or the available) information, usually incomplete; C) Accepting the steady state performance of the dalization QB; D) Interpreting transient results ( AA, AATOT), planning and performing sensitivity studies, modifying the dalization and finally achieving a reference or an acceptable solution. 47/61
48 PARTICIPANTS RESULTS (PHASE II) USER S EFFECT ON BEMUSE Q a, Q b Qa Qb Global Acceptability Factors & AA TOT (AA) tot (AA)tot CEA [C25] IRSN [C25] NRI-2 [A20] GRS [A12] KFKI [A20] UPI [R5] NRI-1 [R5] UPC [R5] KINS [R5] Organization's Name TAEK [R5] PSI [TR4] EDO [T97] JNES [TM55] KAERI [M23] 48/61
49 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) PARTICIPANT S ORGANIZATIONS TO PHASE III PARTICIPANT CEA (France) GRS (Germany) IRSN (France) KAERI (South Korea) KINS (South Korea) NRI-1 (Czech Republic) UPC (Spain) UNIPI (Italy) CODE CATHARE V2.5: 3-D ATHLET 1.2C CATHARE V2.5: 1-D MARS 2.3 RELAP5 / MOD3.3 RELAP5 / MOD3.3 RELAP5 / MOD3.3 RELAP5 / MOD3.2 49/61
50 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) OUTPUT PARAMETERS Time trend TYPE DEFINITION Envelop value of all the rod surface temperatures: Max_TC Upper plenum pressure: P UP Single valued parameter 1 st PCT 2 nd PCT: after t inj Time of accumulator injection: t inj Time of complete quenching: t que OUTPUT UNCERTAIN PARAMETER LOWER UNCERTAINTY BOUND REFERENCE CALCULATION VALUE EXPERIMENTAL VALUE UPPER UNCERTAINTY BOUND 1 st PCT 1062 K 2 nd PCT 1077 K t inj 16.8 s t que 64.9 s 50/61
51 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) 1300 SINGLE VALUE OUTPUT PARAMETERS 1 st PCT: uncertainty bounds temperature (K) lower uncertainty bound reference computation upper uncertainty bound experiment 500 UPC GRS IRSN UNIPI NRI-1 CEA KAERI KINS organisation 51/61
52 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) 1300 SINGLE VALUE OUTPUT PARAMETERS 2 nd PCT: uncertainty bounds temperature (K) lower uncertainty bound reference computation upper uncertainty bound experiment 500 UPC IRSN GRS NRI-1 UNIPI CEA KINS KAERI organisation 52/61
53 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) SINGLE VALUE OUTPUT PARAMETERS time of accumulator injection: uncertainty bounds time (s) lower uncertainty bound reference computation upper uncertainty bound experiment 0 KINS IRSN CEA GRS KAERI UPC NRI-1 UNIPI organisation 53/61
54 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) 120 SINGLE VALUE OUTPUT PARAMETERS time of complete quench: uncertainty bounds time (s) lower uncertainty bound 20 reference computation upper uncertainty bound experiment 0 UPC NRI-1 CEA KAERI UNIPI GRS IRSN KINS organisation 54/61
55 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) temperature (K) CEA Lower uncertainty bound Reference calculation values Upper uncertainty bound Experimental value temperature (K) IRSN Lower uncertainty bound Reference calculation Upper uncertainty bound Experiment temperature (K) time (s) 1400 MAX_TC-59-Lower bound Max_TC-59-Upper bound 1200 NRI-1 Experiment Reference calculation temperature (K) time (s) UPC Lower uncertainty bound Reference calculation values Upper uncertainty bound Experimental value time (s) / time (s)
56 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) Lower uncertainty bound Reference calculation values Upper uncertainty bound Experimental value temperature (K) Lower uncertainty bound Reference calculation values Upper uncertainty bound Experimental value temperature (K) time (s) time (s) UPI Lower Uncertainty Band Reference Calculation Upper Uncertainty Band Experiment temperature (K) temperature (K) Lower uncertainty bound Reference calculation values Upper uncertainty bound Experimental value time (s) / time (s)
57 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) Maximum cladding temperature: width of the uncertainty band 1 st PCT 2 nd PCT complete core quench CEA GRS IRSN KAERI KINS NRI-1 UNIPI UPC temperature (K) time (s) 57/61
58 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) Upper plenum pressure: width of the uncertainty band 5 pressure MPa CEA GRS IRSN KAERI KINS NRI-1 UNIPI UPC time (s) 58/61
59 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) Study performed by KAERI AN INPORTANT OBSERVATION Direct Monte-Carlo: 3500 code runs performed and several sample of 59 or 93 realization From about 1000 the mean value and the 95 % empirical quantile are almost stabilized. The results for the 1 st PCT are: Mean: 1034 K 95% percentile: 1173 K (to be compared to the value 1219 K obtained for step 7 with 93 computations: -46 K) Comparison to Wilks' formula (α = β = 95%, at order 1 and 2): Each 59 computation, the max value is retained Each 93 computation, the 2 nd max value is retained 59/61
60 PARTICIPANTS RESULTS (PHASE III) Mostly taken from Presentation of A. de Crecy, P. Bazin (CEA): 3 rd BEMUSE Meeting Greble, October 2005 (FRANCE) AN INPORTANT OBSERVATION 1400 Reflood PCT (K) Number of Calculations Mean PCT 95% Reflood PCT Wilks 1st order Upper Wilks 2nd order Upper In accordance with Wilks' formula, the 2 nd order determination is less conservative than the 1 st order one Comparison to Wilks' formula (α = β = 95%, at order 1 and 2): 1 st order: among ~58 values [ ] K, -one is significantly lower than the 3500 code run 95 % quantile (5 % of 58 = 3 cases should be expected) 2 nd order: among ~37 values [ ] K, 1 case is found below 1173 K 60/61
61 CONCLUSIONS CONSISTENT AND ADOPTED APPROACHES TO QUANTIFY UNCERTAINTY HAVE BEEN IDENTIFIED: error does t motonically increase with time SUITABLE UNCERTAINTY METHODS EXIST THE BEMUSE PROGRAMME IS AN IMPORTANT STEP ON THE ROAD TO THE RELIABLE APPLICATION TO THE LICENSING PROCESS OF HIGH-QUALITY BEST-ESTIMATE AND UNCERTAINTY EVALUATION METHODS IT ENJOYS WIDE INTERNATIONAL PARTICIPATION AND THE USE OF DIFFERENT COMPUTATIONAL TOOLS (RELAP5, CATHARE, TRACE, ATHLET, MARS, TECH) 61/61
Verification and validation of computer codes Exercise
IAEA Safety Assessment Education and Training (SAET) Programme Joint ICTP- IAEA Essential Knowledge Workshop on Deterministic Safety Assessment and Engineering Aspects Important to Safety Verification
More informationEXPERIMENTAL SUPPORT OF THE BLEED AND FEED ACCIDENT MANAGEMENT MEASURES FOR VVER-440/213 TYPE REACTORS
International Conference Nuclear Energy for New Europe 22 Kranjska Gora, Slovenia, September 9-12, 22 www.drustvo-js.si/gora22 EXPERIMENTAL SUPPORT OF THE BLEED AND FEED ACCIDENT MANAGEMENT MEASURES FOR
More informationLoss of Normal Feedwater Analysis by RELAP5/MOD3.3 in Support to Human Reliability Analysis
Loss of Normal Feedwater Analysis by RELAP5/MOD3.3 in Support to Human Reliability Analysis ABSTRACT Andrej Prošek, Borut Mavko Jožef Stefan Institute Jamova cesta 39, SI-1 Ljubljana, Slovenia Andrej.Prosek@ijs.si,
More informationResearch Article Remarks on Consistent Development of Plant Nodalizations: An Example of Application to the ROSA Integral Test Facility
Science and Technology of Nuclear Installations Volume 22, Article ID 5867, 7 pages doi:.55/22/5867 Research Article Remarks on Consistent Development of Plant Nodalizations: An Example of Application
More informationClassical Event Tree Analysis and Dynamic Event Tree Analysis for High Pressure Core Melt Accidents in a German PWR
OECD International Workshop on Level 2 PSA and Severe Accident Management Koeln, Germany, March 29-31, 2004 Classical Event Tree Analysis and Dynamic Event Tree Analysis for High Pressure Core Melt Accidents
More informationSafety Analysis: Event Classification
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Safety Analysis: Event Classification Lecturer Lesson IV 1_2 Workshop Information IAEA Workshop City, Country XX - XX Month,
More informationEffects of Delayed RCP Trip during SBLOCA in PWR
Effects of Delayed RCP Trip during SBLOCA in PWR Javier Montero Technical University of Madrid, Alenza 4, 28003, Madrid, Spain fj.montero@alumnos.upm.es Cesar Queral, Juan Gonzalez-Cadelo cesar.queral@upm.es,
More informationWorkshop Information IAEA Workshop
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Risk Monitoring tools: Requirements of Risk Monitors, relation with the Living PSA, applications of Risk Monitors Lecturer Lesson
More informationFUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER P: REFERENCE OPERATING CONDITION STUDIES (PCC)
PAGE : 1 / 11 1. PASSIVE SINGLE FAILURE ANALYSIS The aim of the accident analysis in Chapter P is to demonstrate that the safety objectives have been fully achieved, despite the most adverse single failure.
More informationInternational Agreement Report
NUREG/IA-0423 International Agreement Report Analysis with TRACE Code of PKL-III Test F 1.2 Prepared by: J.L. Munoz-Cobo, S. Chiva, A. Escrivá Instituto de Ingenierίa Energética Univesitat Politécnica
More informationExperimental Verification of Integrated Pressure Suppression Systems in Fusion Reactors at In-Vessel Loss-of -Coolant Events
Experimental Verification of Integrated Pressure Suppression Systems in Fusion Reactors at In-Vessel Loss-of -Coolant Events K. Takase 1), H. Akimoto 1) 1) Japan Atomic Energy Research Institute (JAERI),
More informationInternational Agreement Report
NUREG/IA-0408 International Agreement Report IJS Procedure for Converting Input Deck from RELAP5 to TRACE Prepared by: A. Prošek, O.A. Berar, B. Mavko Jožef Stefan Institute Jamova cesta 39 SI-1000 Ljubljana,
More informationDevelopment of a new bench for puncturing of irradiated fuel rods in STAR hot laboratory
Development of a new bench for puncturing of irradiated fuel rods in STAR hot laboratory B. Petitprez, P. Silvestre, P. Valenza, A. Boulore (Fuel Research Department, CEA Cadarache), T. David (Sealing
More informationEvent tree analysis. Prof. Enrico Zio. Politecnico di Milano Dipartimento di Energia. Prof. Enrico Zio
Event tree analysis Politecnico di Milano Dipartimento di Energia Techniques for Risk Analysis Hazard identification: FMEA (Failure Modes and Effects Analysis) & HAZOP (HAZard and OPerability study) Accident
More informationV.H. Sanchez Espinoza and I. Gómez-García-Toraño
V.H. Sanchez Espinoza and I. Gómez-García-Toraño ANALYSIS OF PWR SEVERE ACCIDENT SEQUENCES INCLUDING MITIGATIVE MEASURES TO PREVENT OR DELAY THE FAILURE OF SAFETY BARRIERS WITH THE SEVERE ACCIDENT CODE
More informationJustification of Risk Reduction through In-Service Inspection / REDUCE
NUGENIA+ WP6.12 Justification of Risk Reduction through In-Service Inspection / REDUCE Jens Gunnars Inspecta Technology AB jens.gunnars@inspecta.com WP6.12 Task Leader NUGENIA+ Final Seminar, Helsinki
More informationRELAP5 Code Study of ROSA/LSTF Experiments on PWR Safety System Using Steam Generator Secondary-Side Depressurization
Journal of Energy and Power Engineering 9 (15) 6- doi: 1.1765/193-975/15.5. D DAVID PUBLISHING RELAP5 Code Study of ROSA/LSTF Experiments on PWR Safety System Using Steam Generator Secondary-Side Depressurization
More informationTHE CANDU 9 DISTRffiUTED CONTROL SYSTEM DESIGN PROCESS
THE CANDU 9 DISTRffiUTED CONTROL SYSTEM DESIGN PROCESS J.E. HARBER, M.K. KATTAN Atomic Energy of Canada Limited 2251 Speakman Drive, Mississauga, Ont., L5K 1B2 CA9900006 and M.J. MACBETH Institute for
More informationSENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 440/270 REACTOR
PROCEEDINGS OF THE YEREVAN STATE UNIVERSITY Physical and Mathematical Sciences 216, 2, p. 57 62 P h y s i c s SENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 44/27
More informationPEAPOD. Pneumatically Energized Auto-throttled Pump Operated for a Developmental Upperstage. Test Readiness Review
PEAPOD Pneumatically Energized Auto-throttled Pump Operated for a Developmental Upperstage Test Readiness Review Customer: Special Aerospace Services Chris Webber and Tim Bulk 1 Overview Project Overview
More informationComparison of MARS-KS to SPACE for counter current flow limitation model
Comparison of MARS-KS to SPACE for counter current limitation model Won Woong Lee, Min Gil Kim, Jeong I Lee Department of Nuclear and Quantum engineering, Korea Advanced Institute of Science and Technology
More informationEngineering & Projects Organization
Engineering & Projects Organization Note from : Date: 11/09/2012 To : Copy : N : PEPR-F.10.1665 Rev. 3 Subject: EPR UK - GDA GDA issue FS04 Single Tube Steam Generator Tube Rupture Analysis for the UK
More informationNKS PODRIS project. Importance of inspection reliability assumptions on piping failure probability estimates
NKS PODRIS project Importance of inspection reliability assumptions on piping failure probability estimates Kaisa Simola, Otso Cronvall & Ilkka Männistö (VTT) Jens Gunnars, Peter Dillström & Lars Averlind
More informationPreliminary Failure Mode and Effect Analysis for CH HCSB TBM
Preliminary Failure Mode and Effect Analysis for CH HCSB TBM Presented by: Chen Zhi Contributors by HCSB TBM Safety Group, in China June 21, 2007 E-mail: chenz@swip.ac.cn Outline Introduction FMEA Main
More information1 SE/P-02. Experimental and Analytical Studies on Thermal-Hydraulic Performance of a Vacuum Vessel Pressure Suppression System in ITER
1 SE/P-2 Experimental and Analytical Studies on Thermal-Hydraulic Performance of a Vacuum Vessel Pressure Suppression System in ITER K. Takase 1), H. Akimoto 1) 1) Japan Atomic Energy Research Institute,
More informationSAFETY DEMONSTRATION TESTS ON HTR-10
2nd International Topical Meeting on HIGH TEMPERATURE REACTOR TECHNOLOGY Beijing, CHINA,, September 22-24, 24 #Paper H6 SAFETY DEMONSTRATION TESTS ON HTR-1 Shouyin HU, Ruipian WANG, Zuying GAO Institute
More informationNuclear safety Lecture 4. The accident of the TMI-2 (1979)
Nuclear safety Lecture 4. The accident of the TMI-2 (1979) Ildikó Boros BME NTI 27 February 2017 The China Syndrome Opening: 16 March 1979 Story: the operator of the Ventana NPP tries to hide the safety
More informationCFD SIMULATIONS OF GAS DISPERSION IN VENTILATED ROOMS
CFD SIMULATIONS OF GAS DISPERSION IN VENTILATED ROOMS T. Gélain, C. Prévost Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Saclay, France Abstract In order to better understand the risks due
More informationSafety Classification of Structures, Systems and Components in Nuclear Power Plants
DS367 Draft 5.1 IAEA SAFETY STANDARDS for protecting people and the environment Date: 04/11/2008 Status: for Member States comments Reviewed in NS-SSCS Please submit your comments by 20 March 2009 Safety
More informationA SEMI-PRESSURE-DRIVEN APPROACH TO RELIABILITY ASSESSMENT OF WATER DISTRIBUTION NETWORKS
A SEMI-PRESSURE-DRIVEN APPROACH TO RELIABILITY ASSESSMENT OF WATER DISTRIBUTION NETWORKS S. S. OZGER PhD Student, Dept. of Civil and Envir. Engrg., Arizona State Univ., 85287, Tempe, AZ, US Phone: +1-480-965-3589
More informationAn Improved Modeling Method for ISLOCA for RI-ISI and Other Risk Informed Applications
An Improved odeling ethod for ISLOCA for RI-ISI and Other Risk Informed Applications Young G. Jo 1) 1) Southern Nuclear Operating Company, Birmingham, AL, USA ABSTRACT In this study, an improved modeling
More informationIAEA Training in Level 2 PSA MODULE 8: Coupling Source Terms to Probabilistic Event Analysis (CET end-state binning)
IAEA Training in Level 2 PSA MODULE 8: Coupling Source Terms to Probabilistic Event Analysis (CET end-state binning) The Problem A probabilistic treatment of severe accident progression leads to numerous
More informationVisual Observation of Nucleate Boiling and Sliding Phenomena of Boiling Bubbles on a Horizontal Tube Heater
Proceedings of the 2 nd World Congress on Mechanical, Chemical, and Material Engineering (MCM'16) Budapest, Hungary August 22 23, 216 Paper No. HTFF 146 DOI:.11159/htff16.146 Visual Observation of Nucleate
More informationNE 405/505 Exam 2 Spring 2015
NE 405/505 Exam 2 Spring 2015 (80%) 1) A PWR with UTSGs is operating at 100% power, BOC, with control rods all out in automatic control when a failure in the speed pump controller results in all feed pumps
More informationComparison of the partner s approaches for physical phenomena assessment in level 2 PSA
1/11 Comparison of the partner s approaches for physical phenomena assessment in level 2 PSA J. Eyink, Framatome ANP; H. Löffler, GRS Cologne Abstract Aim of the task 5.1 of the SARNET PSA2 work package
More informationHelium Loop Karlsruhe (HELOKA) large experimental facility for the in-vessel ITER and DEMO components
1 /7-12 Helium Loop Karlsruhe (HELOKA) large experimental facility for the in-vessel IER and DEMO components M. Ionescu-Bujor, B.E. Ghidersa, G. Janeschitz, X. Jin orschungszentrum Karlsruhe, Germany e-mail:
More informationPI MODERN RELIABILITY TECHNIQUES OBJECTIVES. 5.1 Describe each of the following reliability assessment techniques by:
PI 21. 05 PI 21. 05 MODERN RELIABILITY TECHNIQUES OBJECTIVES 5.1 Describe each of the following reliability assessment techniques by: ~) Stating its purpose. i1) Giving an e ample of where it is used.
More informationEnhancing NPP Safety through an Effective Dependability Management
Prepared and presented by Gheorghe VIERU, PhD Senior Scientific Nuclear Security Research Worker AREN/c.o. Institute for Nuclear Research Pitesti, ROMANIA Safety: Defence in Depth, October 2013 1 OUTLINES
More informationDetermination of the Design Load for Structural Safety Assessment against Gas Explosion in Offshore Topside
Determination of the Design Load for Structural Safety Assessment against Gas Explosion in Offshore Topside Migyeong Kim a, Gyusung Kim a, *, Jongjin Jung a and Wooseung Sim a a Advanced Technology Institute,
More informationReview of regulatory framework of Damage Stability of Dry Cargo and Passenger Ships
Review of regulatory framework of Damage Stability of Dry Cargo and Passenger Ships Two main categories of regulatory concepts and methodologies for the assessment of ship s damage stability are nowadays
More informationREGULATORY OBSERVATION
RO unique no.: REGULATORY OBSERVATION REGULATOR TO COMPLETE RO-ABWR-0046 Date sent: 20 th April 2015 Acknowledgement required by: 08 th May 2015 Agreement of Resolution Plan required by: 14 th May 2015
More informationWorkshop Information IAEA Workshop
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Safety Assessment of General Design Aspects of NPPs (Part 2) Lecturer Lesson Lesson III III 1_2 1_2 Workshop Information IAEA
More informationLevel 2 PSA for the VVER 440/213 Dukovany Nuclear Power Plant
Nuclear Nuclear Research Research Institute Řež plc Institute Řež plc Level 2 PSA for the VVER 440/213 Dukovany Nuclear Power Plant Jiří Dienstbier, Stanislav Husťák OECD International Workshop on Level-2
More informationAssessing Combinations of Hazards in a Probabilistic Safety Analysis
Assessing Combinations of Hazards in a Probabilistic Safety Analysis Halbert Taekema a, and Hans Brinkman a a NRG, Arnhem, The Netherlands Abstract: Guidance on how to systematically address combination
More informationSAFETY APPROACHES. The practical elimination approach of accident situations for water-cooled nuclear power reactors
SAFETY APPROACHES The practical elimination approach of accident situations for water-cooled nuclear power reactors 2017 SUMMARY The implementation of the defence in depth principle and current regulations
More informationPOWER Quantifying Correction Curve Uncertainty Through Empirical Methods
Proceedings of the ASME 2014 Power Conference POWER2014 July 28-31, 2014, Baltimore, Maryland, USA POWER2014-32187 Quantifying Correction Curve Uncertainty Through Empirical Methods ABSTRACT Christopher
More informationIMO REVISION OF THE INTACT STABILITY CODE. Proposal of methodology of direct assessment for stability under dead ship condition. Submitted by Japan
INTERNATIONAL MARITIME ORGANIZATION E IMO SUB-COMMITTEE ON STABILITY AND LOAD LINES AND ON FISHING VESSELS SAFETY 49th session Agenda item 5 SLF 49/5/5 19 May 2006 Original: ENGLISH REVISION OF THE INTACT
More informationRISKAUDIT GRS - IRSN Safety assessment of the BELENE NPP
RISKAUDIT GRS - IRSN Safety assessment of the BELENE NPP Bulatom Conference 2010 Bulgarian Nuclear Energy National, Regional and World Energy Safety 9th -11th June 2010, Riviera complex, Varna Système
More informationReview and Assessment of Engineering Factors
Review and Assessment of Engineering Factors 2013 Learning Objectives After going through this presentation the participants are expected to be familiar with: Engineering factors as follows; Defense in
More informationASVAD THE SIMPLE ANSWER TO A SERIOUS PROBLEM. Automatic Safety Valve for Accumulator Depressurization. (p.p.)
ASVAD Automatic Safety Valve for Accumulator Depressurization (p.p.) THE SIMPLE ANSWER TO A SERIOUS PROBLEM International Experts Meeting on Strengthening Research and Development Effectiveness in the
More informationSystems of Accounting for and Control of Nuclear Material
Systems of Accounting for and Control of Nuclear Material STATES' OBLIGATIONS TO ESTABLISH AN ACCOUNTING AND CONTROL SYSTEM The implementation of safeguards agreements has always involved governmental
More informationMDEP Common Position No AP
MDEP Validity: until net update or archiving MDEP Common Position No AP1000-01 Related to : AP1000 Working Group activities THE DESIGN AND USE OF EXPLOSIVE - ACTUATED (SQUIB) VALVES IN NUCLEAR POWER PLANTS
More informationTransient Analyses In Relief Systems
Transient Analyses In Relief Systems Dirk Deboer, Brady Haneman and Quoc-Khanh Tran Kaiser Engineers Pty Ltd ABSTRACT Analyses of pressure relief systems are concerned with transient process disturbances
More informationCFD Based Approach for VCE Risk Assessment
CFD Based Approach for VCE Risk Assessment 2009 MKOPSC International Symposium Anna Qiao, Steven Zhang, Asmund Huser DNV Energy Objective Determine the maximum design load at a specified frequency Provide
More informationTechnical Standards and Legislation: Risk Based Inspection. Presenter: Pierre Swart
Technical Standards and Legislation: Risk Based Inspection Presenter: Pierre Swart Agenda Change in Legislation. Where RBI fits in. Application to implement RBI. RBI concepts. Elements of an RBI analysis.
More informationMIL-STD-883G METHOD
STEADY-STATE LIFE 1. PURPOSE. The steady-state life test is performed for the purpose of demonstrating the quality or reliability of devices subjected to the specified conditions over an extended time
More informationInjector Dynamics Assumptions and their Impact on Predicting Cavitation and Performance
Injector Dynamics Assumptions and their Impact on Predicting Cavitation and Performance Frank Husmeier, Cummins Fuel Systems Presented by Laz Foley, ANSYS Outline Overview Computational Domain and Boundary
More informationQuantitative Risk of Linear Infrastructure on Permafrost Heather Brooks, PE. Arquluk Committee Meeting November 2015
Slide 1 Quantitative Risk of Linear Infrastructure on Permafrost Heather Brooks, PE Arquluk Committee Meeting November 2015 Welcome to the meeting of the committee for Arquluk s Quantitative Risk of Linear
More informationGUIDELINES ON OPERATIONAL INFORMATION FOR MASTERS IN CASE OF FLOODING FOR PASSENGER SHIPS CONSTRUCTED BEFORE 1 JANUARY 2014 *
E 4 ALBERT EMBANKMENT LONDON SE1 7SR Telephone: +44 (0)20 7735 7611 Fax: +44 (0)20 7587 3210 MSC.1/Circ.1589 24 May 2018 GUIDELINES ON OPERATIONAL INFORMATION FOR MASTERS IN CASE OF FLOODING FOR PASSENGER
More informationQuantitative Risk Analysis (QRA)
Quantitative Risk Analysis (QRA) A realistic approach to relief header and flare system design Siemens AG 2017, All rights reserved 1 Quantitative Risk Analysis Introduction Most existing pressure relief
More informationSTART UP MODELING OF KAIST MICRO MODULAR REACTOR COMPRESSOR USING BETA LINE METHOD WITH GAMMA+ CODE
The 6th International Supercritical CO2 Power Cycles Symposium March 27-29, 2018, Pittsburgh, Pennsylvania START UP MODELING OF KAIST MICRO MODULAR REACTOR COMPRESSOR USING BETA LINE METHOD WITH GAMMA+
More informationDevelopment of Prediction Models for Spent Nuclear Fuel Storage Cask Monitoring Hyong Chol Kim, Sam Hee Han, Dong Jae Park
Transactions of the Korean Nuclear Society Autumn Meeting Yeosu, Korea, October 25-26, 2018 Development of Prediction Models for Spent Nuclear Fuel Storage Cask Monitoring Hyong Chol Kim, Sam Hee Han,
More informationHEALTH AND SAFETY EXECUTIVE HM NUCLEAR INSTALLATIONS INSPECTORATE
HEALTH AND SAFETY EXECUTIVE HM NUCLEAR INSTALLATIONS INSPECTORATE New Reactor Generic Design Assessment (GDA) - Step 2 Preliminary Review Assessment of: Structural Integrity Aspects of AREVA/EdF EPR HM
More informationTest Plans & Test Results
P09051 Oxygen Gas Sensor Test Plans & Test Results By: Samuel H Shin (EE), Jeremy Goodman (ue) Table of contents 1. TITLE: OXYGEN MEASUREMENT TEST VIA FABRICATED OXYGEN GAS SENSOR SYSTEM... 2 1.1. Introduction...
More informationSports Analytics: Designing a Volleyball Game Analysis Decision- Support Tool Using Big Data
Sports Analytics: Designing a Volleyball Game Analysis Decision- Support Tool Using Big Data Sarah Almujahed, Nicole Ongor, John Tigmo, Navjot Sagoo Abstract From 2006-2012, George Mason University s (GMU)
More informationRecent Research on Hazards PSA
Recent Research on Hazards PSA Marina Röwekamp, Hartmut Holtschmidt, Michael Türschmann Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) ggmbh IEM8 - International Experts Meeting on Strengthening
More informationActive Control of Vapor Pressurization (VaPak) Systems
Active Control of Vapor Pressurization (VaPak) Systems Ralph Ewig, PhD Holder Consulting Group, Renton, WA 98059, USA Vapor pressurized (VaPak) propellant feed systems hold great promise for the development
More informationAeroelasticity of Turbomachines
MUSAF II Colloquium, Toulouse, France Aeroelasticity of Turbomachines Damian Vogt, formerly KTH (now University of Stuttgart) Torsten Fransson, KTH 2013-09-18 (Giles, 1991) 2 Content of Today s Talk Crash
More informationDETAILS OF THE ACCIDENT PROGRESSION IN 1F1
DETAILS OF THE ACCIDENT PROGRESSION IN 1F1 EMUG 2019 BRAUN, Matthias Switzerland, 3 rd -5 th April 2019 Not part of the BSAF OECD Benchmark Project Relying exclusively on publically available input data
More informationSafety assessments for Aerodromes (Chapter 3 of the PANS-Aerodromes, 1 st ed)
Safety assessments for Aerodromes (Chapter 3 of the PANS-Aerodromes, 1 st ed) ICAO MID Seminar on Aerodrome Operational Procedures (PANS-Aerodromes) Cairo, November 2017 Avner Shilo, Technical officer
More informationEvaluation and Demonstration of Safety of Decommissioning of
Evaluation and Demonstration of Safety of Decommissioning of Research Reactors Borislava Batandjieva, IAEA Research Reactor Decommissioning Demonstration Project (R2D2P) 26-30 June 2006, Manila, Philippines
More informationExekon. Nuclear. ý C)C) ý. May 9, 2001 SVP U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
Exelon Generation Ouad Cities Generating Station 22710 206th Avenue North Cordova, I L 61242-9740 Tel 309-654-2241 May 9, 2001 www.exelon corp.com Exekon. Nuclear SVP-01-059 U. S. Nuclear Regulatory Commission
More informationNext Generation Quartz Pressure Gauges
Next Generation Quartz Pressure Gauges Rick Puccio, Ph.D. Senior Scientist Quartzdyne Houston, TX March 2, 2016 Outline Quartz Pressure Gauge Introduction Gauge Size Reduction Long Term Pressure Drift
More informationOptimization of a Wing-Sail shape for a small boat
STAR Global Conference 2014 Vienna, March 17-19 Optimization of a Wing-Sail shape for a small boat G. Lombardi, F. Cartoni, M. Maganzi Dept. of Civil and Industrial Engineering of Pisa Aeronautical Section
More informationTHE FUNDAMENTALS OF THE AIR SAMPLER CALIBRATION-VERIFICATION PROCESS
THE FUNDAMENTALS OF THE AIR SAMPLER CALIBRATION-VERIFICATION PROCESS Frank M. Gavila F&J SPECIALTY PRODUCTS, INC. 404 Cypress Road Ocala, Florida, USA 3447 fandj@fjspecialty.com INTRODUCTION The calibration
More informationThe Use of a Process Simulator to Model Aeration Control Valve Position and System Pressure
The Use of a Process Simulator to Model Aeration Control Valve Position and System Pressure Matthew Gray 1 * and Steve Kestel 1 1 BioChem Technology, King of Prussia, PA *Email: mgray@biochemtech.com ABSTRACT
More informationFIRE PROTECTION. In fact, hydraulic modeling allows for infinite what if scenarios including:
By Phil Smith, Project Manager and Chen-Hsiang Su, PE, Senior Consultant, Lincolnshire, IL, JENSEN HUGHES A hydraulic model is a computer program configured to simulate flows for a hydraulic system. The
More informationUKAS calibration laboratory 8809 Temperature, pressure and electrical signals calibration guide
ABB MEASUREMENT & ANALYTICS PRODUCT GUIDE PG/SMD140 EN REV. B UKAS calibration laboratory 8809 Temperature, pressure and electrical signals calibration guide Measurement made easy UKAS calibration laboratory
More informationZIN Technologies PHi Engineering Support. PHi-RPT CFD Analysis of Large Bubble Mixing. June 26, 2006
ZIN Technologies PHi Engineering Support PHi-RPT-0002 CFD Analysis of Large Bubble Mixing Proprietary ZIN Technologies, Inc. For nearly five decades, ZIN Technologies has provided integrated products and
More informationRegulatory requirements with respect to Spent Fuel Pool Cooling
Regulatory requirements with respect to Spent Fuel Pool Cooling Dr. Christoph Pistner Annual Meeting on Nuclear Technology Hamburg, 12.05.2016 Important Documents Safety Requirements for Nuclear Power
More informationTESTING OF BELIMO PRESSURE INDEPENDENT CHARACTERIZED CONTROL VALVES
TESTING OF BELIMO PRESSURE INDEPENDENT CHARACTERIZED CONTROL VALVES November, 25 Submitted by: Iowa Energy Center Address: DMACC, 26 S. Ankeny Blvd. Ankeny, IA 521 Phone: 515.965.755 Fax: 515.965.756 Web
More informationProfile LFR-43 HELENA ITALY. Italian National Agency for New Technologies, Energy and Sustainable Economic Development, C.R. ENEA Brasimone, Italy
Profile LFR-43 HELENA ITALY GENERAL INFORMATION NAME OF THE FACILITY ACRONYM COOLANT(S) OF THE FACILITY LOCATION (address): OPERATOR CONTACT PERSON (name, address, institute, function, telephone, email):
More informationEMERGENCY CORE COOLING SYSTEM SIMPLIFICATION
EMERGENCY CORE COOLING SYSTEM SIMPLIFICATION XA9846601 R.S. HART Sheridan Park Research Community, Atomic Energy of Canada Ltd, Mississauga, Ontario D.B. RHODES Chalk River Laboratories, Atomic Energy
More information(2 pts) Draw the line of best fit through the data and estimate the concentration of Fe in your sample solution.
Name: 1. You are asked to measure the percent iron in a steel sample you believe to be about 50% Fe by mass. You dissolve four replicate samples in nitric acid and dilute them by mass to a concentration
More informationMISTRA Facility for Containment Lumped Parameter and CFD Codes Validation: Example of the International Standard Problem ISP47
International Conference Nuclear Energy for New Europe 2005 Bled, Slovenia, September 5-8, 2005 MISTRA Facility for Containment Lumped Parameter and CFD Codes Validation: Example of the International Standard
More informationAnalysis of hazard to operator during design process of safe ship power plant
POLISH MARITIME RESEARCH 4(67) 2010 Vol 17; pp. 26-30 10.2478/v10012-010-0032-1 Analysis of hazard to operator during design process of safe ship power plant T. Kowalewski, M. Sc. A. Podsiadło, Ph. D.
More informationInspection Credit for PWSCC Mitigation via Peening Surface Stress Improvement
Inspection Credit for PWSCC Mitigation via Peening Surface Stress Improvement Glenn A. White, Kyle P. Schmitt, Kevin J. Fuhr, Markus Burkardt, and Jeffrey A. Gorman Dominion Engineering, Inc. Paul Crooker
More informationMain Insights and Perspectives of Pool scrubbing Research: Examples of THAI and NUGENIA/IPRESCA
Main Insights and Perspectives of Pool scrubbing Research: Examples of THAI and NUGENIA/IPRESCA Sanjeev GmbH, Germany gupta@becker-technologies.com February 28 th, 2017 Pool scrubbing - Introduction Definition
More informationInvestigation of Inspection Performance on Cracked Railway Axles
ECNDT 2006 - Fr.1.3.2 Investigation of Inspection Performance on Cracked Railway Axles John RUDLIN, Amin MUHAMMED, Charles SCHNEIDER TWI Limited, Cambridge, UK Abstract. Failure of railway axles, although
More informationLab 1c Isentropic Blow-down Process and Discharge Coefficient
058:080 Experimental Engineering Lab 1c Isentropic Blow-down Process and Discharge Coefficient OBJECTIVES - To study the transient discharge of a rigid pressurized tank; To determine the discharge coefficients
More informationChapter 2 Ventilation Network Analysis
Chapter 2 Ventilation Network Analysis Abstract Ventilation network analysis deals with complex working procedures to calculate the air currents flowing in the various meshes or branches of a mine network.
More informationMIKE NET AND RELNET: WHICH APPROACH TO RELIABILITY ANALYSIS IS BETTER?
MIKE NET AND RELNET: WIC APPROAC TO RELIABILITY ANALYSIS IS BETTER? Alexandr Andrianov Water and Environmental Engineering, Department of Chemical Engineering, Lund University P.O. Box 124, SE-221 00 Lund,
More informationIAEA SAFETY STANDARDS for protecting people and the environment
IAEA SAFETY STANDARDS for protecting people and the environment DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS DRAFT SAFETY GUIDE DS 482 STATUS: STEP 11 Submission to Review
More informationROAD SAFETY DEVELOPMENT INDEX (RSDI)
ROAD SAFETY DEVELOPMENT INDEX (RSDI) Dept of Science and Technology (ITN), Linköping University, 60 74 Norrköping, Sweden Phone: +46 36 33 73 Fax: +46 36 32 70 E-mail: ghaal@itn.liu.se Ghazwan al-haji,
More informationNUBIKI Nuclear Safety Research Institute, Budapest, Hungary
System Reliability Analysis and Probabilistic Safety Assessment to Support the Design of a New Containment Cooling System for Severe Accident Management at NPP Paks Tamas Siklossy* a, Attila Bareith a,
More informationAcid Gas Progress Report Requirements
Acid Gas Progress Report Requirements Operation of an acid gas disposal well requires the permit holder to submit a Progress Report to the Commission twice a year, filed within 60 days after the end of
More informationAutodesk Moldflow Communicator Process settings
Autodesk Moldflow Communicator 212 Process settings Revision 1, 3 March 211. Contents Chapter 1 Process settings....................................... 1 Profiles.................................................
More informationMASSIVE GAS INJECTION SYSTEMS FOR DISRUPTION MITIGATION ON THE DIII-D TOKAMAK
MASSIVE GAS INJECTION SYSTEMS FOR DISRUPTION MITIGATION ON THE DIII-D TOKAMAK T. C. Jernigan, L. A. Baylor, and S. K. Combs Oak Ridge National Laboratory D. A. Humphreys, P. B. Parks, and J. C. Wesley
More informationHTR Systems and Components
IAEA Course on HTR Technology Beijing, 22-26.October 2012 HTR Systems and Components Dr. Gerd Brinkmann Dieter Vanvor AREVA NP GMBH Henry-Dunant-Strasse 50 91058 Erlangen phone +49 9131 900 96840/95821
More informationSDO MECHANICAL CODES CONVERGENCE BOARD:
4 TH MDEP CONFERENCE, SESSION 1: CODES AND STANDARDS HARMONIZATION SDO MECHANICAL CODES CONVERGENCE BOARD: ACHIEVEMENTS & PERSPECTIVES Presented By: Philippe Malouines, on behalf of the SDO board members
More information