17th Symposium of AER on VVER Reactor Physics and Reactor Safety, 24-28 September 2007, Yalta, Crimea, Ukraine INNOVATIONS IN MOBY-DICK CODE Šůstek J.,Krýsl.

Slides:



Advertisements
Similar presentations
Jesper H. Sørensen, Toshiaki Koike-Akino, and Philip Orlik 2012 IEEE International Symposium on Information Theory Proceedings Rateless Feedback Codes.
Advertisements

TRANSIENT EVALUATION OF A GEN-IV LFR DEMONSTRATION PLANT THROUGH A LUMPED-PARAMETER ANALYSIS OF COUPLED KINETICS AND THERMALHYDRAULICS ANALYSIS OF COUPLED.
Idaho National Engineering and Environmental Laboratory SCWR Preliminary Safety Considerations Cliff Davis, Jacopo Buongiorno, INEEL Luca Oriani, Westinghouse.
The Normal Distribution
Experiments and Variables
BEZIER CURVES Part II. Assume we are given two endpoints labelled E1 and E2 and two control points labelled C1 and C2. create a smooth curve whose endpoints.
Nuclear Reactor Theory, JU, First Semester, (Saed Dababneh). 1 Reactor Model: One-Group That was for the bare slab reactor. What about more general.
Issues Associated with the Development of Severe Accident Management Guidelines for CANDU Reactors Keith Dinnie Director, Risk Management Nuclear Safety.
HTTF Analyses Using RELAP5-3D Paul D. Bayless RELAP5 International Users Seminar September 2010.
Investigation of "dry" recriticality of the melt during late in-vessel phase of severe accident in Light Water Reactor D.Popov, KNPP, BG O.Runevall, KTH,
PHYS-H406 – Nuclear Reactor Physics – Academic year CH.VI: REACTIVITY BALANCE AND REACTOR CONTROL REACTIVITY BALANCE OPERATION AND CONTROL.
Development of Dynamic Models Illustrative Example: A Blending Process
1 THERMAL LOADING OF A DIRECT DRIVE TARGET IN RAREFIED GAS B. R. Christensen, A. R. Raffray, and M. S. Tillack Mechanical and Aerospace Engineering Department.
Lecture of : the Reynolds equations of turbulent motions JORDANIAN GERMAN WINTER ACCADMEY Prepared by: Eng. Mohammad Hamasha Jordan University of Science.
5.5 The Substitution Rule. The Substitution Rule If u=g(x) is differentiable function whose range is an interval I, and f is continuous on I, then The.
Chapter 6 Random Error The Nature of Random Errors
COMPARATIVE NUCLEAR SAFETY ANALYSIS OF REGULAR AND COMPACT SPENT FUEL STORAGE AT CHORNOBYL NPP Yu. Kovbasenko, Y. Bilodid, V. Khalimonchuk, State Scientific.
Argonne National Laboratory 2007 RELAP5 International User’s Seminar
INSTANT/PHISICS – RELAP5 coupling A. Epiney, C. Rabiti, Y. Wang, J. Cogliati, T. Grimmett, P. Palmiotti.
А Е Ц “К О З Л О Д У Й” - Е А Д N P P K O Z L O D U Y – P L C 17 th Symposium of AER Y alta, Crimea, September 24-28, 2007 WWER-1000 SPENT FUEL NUCLIDE.
Fundamentals of Neutronics : Reactivity Coefficients in Nuclear Reactors Paul Reuss Emeritus Professor at the Institut National des Sciences et Techniques.
17th Symposium of AER, Yalta, Crimea, Ukraine, Sept , 2007.
1 17 th Symposium of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007, Yalta, Crimea, Ukraine FUEL PERFORMANCE AND OPERATION EXPERIENCE.
Nuclear Research Institute Řež plc 1 DEVELOPMENT OF RELAP5-3D MODEL FOR VVER-440 REACTOR 2010 RELAP5 International User’s Seminar West Yellowstone, Montana.
An Iterative General Planetary Theory P. K. Seidelmann University of Virginia.
MODELLING OF THE VVER-440 REACTOR FOR DETERMINATION OF THE SPATIAL WEIGHT FUNCTION OF EX-CORE DETECTORS USING MCNP-4C2 CODE Gabriel Farkas, Vladimír Slugeň.
Nuclear Fuels Storage & Transportation Planning Project Office of Fuel Cycle Technologies Nuclear Energy Criticality Safety Assessment for As-loaded Spent.
KINEMATICS Kinematics describes fluid flow without analyzing the forces responsibly for flow generation. Thereby it doesn’t matter what kind of liquid.
1 SEVERAL REMARKS ON THE FUEL CYCLE ECONOMY Roman Kubín, Rudolf Vespalec ALTA, a.s. CZECH REPUBLIC 17 th AER Symposium - September 2007, Yalta.
,Yalta,17-th Symposium of AER1 IMPACT OF CHANGED FUEL PERFORMANCES ON SAFETY BARRIER EFFECTIVENESS AT NORMAL OPERATION OF NPP WITH VVER A.V.
Big Ideas Differentiation Frames with Icons. 1. Number Uses, Classification, and Representation- Numbers can be used for different purposes, and numbers.
Radiation Heating of Thermocouple above Fuel Assembly.
1 prezentácia VUJE, Inc., Okružná 5, Trnava, Slovak Republic K. Klučárová, J. Remiš, M. Závodský, V. Petényi VUJE, Inc. 17th Symposium of AER, Sept.
Reduction of Spent Fuel Volume by Optimisation of VVER- 440 Fuel Assembly AER Meeting, Working Group F Liblice, Czech Republic April 10 – 12,
IAEA Meeting on INPRO Collaborative Project “Performance Assessment of Passive Gaseous Provisions (PGAP)” December, 2011, Vienna A.K. Nayak, PhD.
1 RRC KI Reduced leakage 17th Symposium of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007, Yalta, Crimea, Ukraine ADVANCED FUEL CYCLES.
USE OF THE AXIAL BURNUP PROFILE AT THE NUCLEAR SAFETY ANALYSIS OF THE VVER-1000 SPENT FUEL STORAGE FACILITY IN UKRAINE Olena Dudka, Yevgen Bilodid, Iurii.
KFKI Atomic Energy Research Institute Statistical evaluation of the on line core monitoring effectiveness for limiting the consequences of the fuel assembly.
INVESTIGATION HELPS Planning your investigation. INVESTIGATION HELPS Introduction For a fixed resistance there is a relationship between R, V and I. Plotting.
СRCD NSC KIPT DiFis 2.0 – 3D Finite Element Neutron Kinetic Code A.I. Zhukov and A.M. Abdullayev NSC Kharkov Institute of Physics and Technology September.
Quality Control: Analysis Of Data Pawan Angra MS Division of Laboratory Systems Public Health Practice Program Office Centers for Disease Control and.
Task 2.1: Review of ELSY and Conceptual design & neutronic characterization of the ELFR Industrial Plant Kamil Tuček on behalf of Task 2.1 contributors.
17th Symposium of AER, Yalta Information about WG A th Symposium of AER Yalta, Ukraine, September 24-29, 2007 INFORMATION ABOUT AER WORKING GROUP.
17th Symposium of AER Yalta, Ukraine, September 24-29, 2007 Extension of VVER-440 fuel cycles using improved FA design Pavel Mikoláš
C N S Presentation T E A M B. Malfunction A #1 (Drop of all control rods in CBA)
Warm Up. Solving Differential Equations General and Particular solutions.
V.M. Sliusar, V.I. Zhdanov Astronomical Observatory, Taras Shevchenko National University of Kyiv Observatorna str., 3, Kiev Ukraine
Using Modelling to Address Problems Scientific Enquiry in Biology and the Environmental Sciences Modelling Session 2.
1 State Scientific and Technical Center on Nuclear and Radiation Safety THE THERMAL-MECHANICAL BEHAVIOR OF FUEL PINS DURING POWER'S MANEUVERING REGIME.
COMPARATIVE ANALYSIS OF DIFFERENT METHODS OF MODELING OF MOST LOADED FUEL PIN IN TRANSIENTS Y.Ovdiyenko, V.Khalimonchuk, M. Ieremenko State Scientific.
APPLICATION OF CLUSTER ANALYSIS AND AUTOREGRESSIVE NEURAL NETWORKS FOR THE NOISE DIAGNOSTICS OF THE IBR-2M REACTOR Yu. N. Pepelyshev, Ts. Tsogtsaikhan,
RRC “Kurchatov Institute”, Russia NEUTRONIC AND THERMAL HYDRAULIC CODE PACKAGE PERMAK-3D/SC-1 IN 3D PIN-BY-PIN ANALYSIS OF THE VVER CORE P.А. Bolobov,
© Copyright 2016 OGF - Polling – Reactivity Coefficients Reactivity Coefficients Rx Theory.
Panel Discussion: Discussion on Trends in Multi-Physics Simulation
Date of download: 10/13/2017 Copyright © ASME. All rights reserved.
MODUL KE ENAM TEKNIK MESIN FAKULTAS TEKNOLOGI INDUSTRI
Thermodynamics Thermal Hydraulics.
From: Flow Boiling in an In-Line Set of Short Narrow Gap Channels
International Workshop
Fundamentals Data processing concepts
Chemical Reaction Engineering (CRE) is the field that studies the rates and mechanisms of chemical reactions and the design of the reactors in which.
SCWR Thermal-Hydraulic Instability Analysis
Statistical Methods For Engineers
Data transfer between codes
5. EXPERIMENT Material: Instrument Experiment condition:
Can All Research Reactors be Fueled only with LEU in the Future?
CHAPTER – 1.2 UNCERTAINTIES IN MEASUREMENTS.
The structure and evolution of stars
Egyptian Atomic Energy Authority (EAEA), Egypt
Presentation transcript:

17th Symposium of AER on VVER Reactor Physics and Reactor Safety, September 2007, Yalta, Crimea, Ukraine INNOVATIONS IN MOBY-DICK CODE Šůstek J.,Krýsl V. ŠKODA JS a.s., Orlík 266, Plzeň Czech Republic

During using of the macrocode Moby-Dick has surfaced that structure of the program has some limitations in accuracy of calculations. Many of these limitations originate in extensive using of the low precision representation of the real variables. Increase of precision should allow to remove some non- physical artifacts of calculations, overall increase accuracy of calculations and allow to do types of calculations not possible before.

Our idea was quite simple: replace old representation of real variables, which use single precision, with double precision representation. single precision ~ 7 digits (4 bytes) double precision ~15 digits (8 bytes) Task was not quite easy, we had to rewrite many parts of macrocode. We have used this opportunity to modernize internal structure of macrocode, which now uses memory more effectively.

EFFECTS OF INCREASED PRECISION Generally speaking, effect of increased precision is “smoothing” of results. Tests show that influence on normal calculations, for example core-mesh and pin-wise calculations in 60deg symmetry, is negligible. But when we calculate full- core case, slight asymmetries among symmetrical parts of core for single precision variables can be found, especially in pin-wise model. In the past, we couldn’t average them out, as values of criteria of convergence didn’t allow us to put them more precisely. But as we can use increased precision of criterions, we can completely remedy this situation.

In first example we want to show two examples of this “smoothing”. First case is calculations of the integral and differential reactivity of the control assembly (CA). Calculations were made for EDU NPP, unit 3, cycle 19 for end of the cycle (EOC), reactor at nominal power. Second case is evolution of the power of the reactor when perturbation in the size of the coolant flow occurs. Calculations were made for EDU NPP, unit 3, cycle 28 for beginning of the cycle (BOC), reactor at nominal power. Perturbation is change of the coolant flow, with its increase of 5%.

Fig.1 Calculations of the integral and differential reactivity of the control assembly, single precision

Fig. 2 Calculations of the integral and differential reactivity of the control assembly, double precision

Fig. 3 Evolution of power of the reactor after perturbation of coolant flow, single precision

Fig. 4 Evolution of power of the reactor after perturbation of coolant flow, double precision

In second example we used new precision to compare reactivity coefficients calculated by the perturbation theory (using adjoint fluxes) and by direct calculation. Direct calculation means that we precisely calculate base state (unperturbed) and change value of required quantity, with other parameters of the core unchanged. After that we use difference in reactivities and amount of changed quantity and directly calculate appropriate reactivity coefficient. Concentrations of Xe and Sm are during calculation of the perturbed state as in basic state. Calculations were made for EDU NPP, unit 3, cycle 24, for several moments during the cycle, from which we chose to present state with effective time 2 days. Reactor is at nominal power, and all other parameters are also nominal.

In following pictures we can compare results of both different methods of calculations, for different values of perturbations. Perturbation theory calculations are denoted as “petr”, while direct calculations as “trap”. We must note that using single precision, direct calculations of reactivity coefficients are impossible. Calculations shown include boron reactivity coefficient, moderator density coefficient, (input) moderator temperature coefficient, coolant flow reactivity coefficient and fuel temperature coefficient.

Fig. 5 Boron reactivity coefficient, comparison of the perturbation theory and direct calculation

Fig. 6 Moderator density coefficient, comparison of the perturbation theory and direct calculation

Expected result for all cases is that curves for both types of calculations – direct and using perturbation theory – shall meet in limit for undisturbed state, hopefully with the same angular coefficient. As we can see from results, this condition is met for boron reactivity coefficient and moderator density coefficient. Other coefficients (coolant flow reactivity coefficient, moderator temperature coefficient and fuel temperature coefficient) show discrepancies, albeit fuel temperature coefficient only small. We are currently investigating cause of these discrepancies.

Fig. 7 (input) moderator temperature coefficient, comparison of the perturbation theory and direct calculation

Fig. 8 Coolant flow reactivity coefficient, comparison of the perturbation theory and direct calculation

Fig. 9 Fuel temperature coefficient, comparison of the perturbation theory and direct calculation