Activity on Fast Reactor in Slovakia - Atoms for Peace and ... · Activity on Fast Reactor in...

Activity on Fast Reactor in Slovakia

Ján Haščík, [email protected]

Institute of Nuclear and Physical Engineering STU in Bratislava

FEI STU

47th IAEA Technical Working Group on Fast Reactors Vienna

2014 2

Content

Experience of neutronic group

Computational schemes and tools

Strategies for further research of fast reactor systems

Further activity

FEI STU


2014 3

Experience in the field of design studies

NPP Mochovce (3 years) – Implementation of new fuel type to the operation of WWER reactors

CEA (3 month) – Investigation of the new capabilities of proposed SFR core designs,

KAERI (1 year) – Development of utilities aimed on optimization of neutron cross section data sets for design studies reactor core and radiation shield optimization of the Korean space reactor

FEI STU


2014 4

Experience in the field of design studies 2

GoFastR (1year) – ALLEGRO and GFR2400 core analyses

Scientific papers - FR13, Nuclear Data Files, in publication

Near Future – studies related to reactivity control systems, calculation bias, uncertainties, reactivity feedback effects and kinetics.

FEI STU


2014 5

CEA – Reactivity Coefficients and Transmutation

Optimization of safety feedback coefficients by introducing a moderator into the SFR reactor core :

o An effort was made to limit the excess reactivity and the void effect of the SFR reactor core, since these effects are associated with transient initiating general core melting.

FEI STU


2014 6

CEA – Reactivity Coefficients and Transmutation 2

Minor Actinides Transmutation in a depleted UO2 filled blanket zone of the SFR:

o For 3 basic minor actinides compositions the utilization of BeO, MgO, Li2O, SiC and ZrH2 moderators was investigated. Transmutation rates, decay heat production, He production, source terms and many other parameters were analysed and compared to the reference composition ,without moderator.

For the simulations the French deterministic ERANOS2.2 code was used

FEI STU


2014 7

NPP Mochovce- Criticality Safety analyses

Criticality safety analysis of spent fuel storage of NPP MOCHOVCE using MCNP5,

Verification of neutron power density distribution of the 2nd unit of the Mochovce NPP for the 12. fuel loading campaign, using the MCNP5 and SCALE codes.

Figure : MCNP model of compact grid of the spent

fuel storage pool – horizontal cross section. (Variant C2 (D2) – loading with 4.87 %

enriched FAs and four rows of 45 MWd/kg (50 MWd/kg)

burned FAs.)

FEI STU


2014 8

International GoFastR project

Associate member of the 7-th framework GoFastR project,

Individual and cooperative works with BME Budapest and VUJE, a.s. Trnava,

Calculations performed on GFR2400:

Participation on the neutronic benchmark

FEI STU


2014 9

International GoFastR project 2

Calculations performed on the MOX and ceramic pin

type ALLEGRO reactor cores: o Doppler effect

o Depressurization reactivity

o Control rod efficiency

o Burn-up calculations

FEI STU


2014 10

KAERI - Sensitivity & uncertainty, cross section adjustment

APSTRACT

Analyzer of Perturbation and Sensitivity with TRAnsport Calculation application of standard perturbation Theory to determine sensitivity of keff on cross section data. Identification of important processes and evaluation of the influence of variation in input parameter based on the estimation of a change of the system response due to change in this parameter. Capable to determine sensitivities to reactivity response and to decompose the integral reactivity in terms of space or material.

FEI STU


2014 11

KAERI - Sensitivity & uncertainty, cross section adjustment 2

ATCROSS

Adjustment Tool for CROSs Section data. Conventional cross section adjustment method was applied to evaluate cross section data as much as possible within their error limits and taking into account the correlations, in such way, that a better agreement between calculated results and measured integral data is obtained. In addition, the determination of cross section uncertainty propagation on evaluated results was implemented to the code.

FEI STU


2014 12

International Conference on Fast Reactors and Related Fuel Cycles, Safe Technologies and Sustainable Scenarios – FR13

Investigation of the Coupled effects of Movable Reflector and Safety Control Rods in the GFR 2400

Calculation of Void and Doppler Coefficients Identification and analyses of decoupled neutronic

zones in the GFR 2400 core Performed by the MCNP5 and KENO6 codes with

ENDF/B VII.0 libraries

FEI STU


2014 13

Sensitivity and Uncertainty Analysis of the ALLEGRO MOX Fuel Subassembly

Utilization of the TSUNAMI-3D module of the SCALE6 system

238-group ENDF/B VII.0 incident-neutron data libraries with 44-group SCALE covariance data

Identification of appropriate criticality-safety benchmark experiments

Calculation of sensitivity profiles for keff and specific ENDF reactions,

Investigation of the spatial distribution of integral sensitivities.

FEI STU


2014 14

Available computational tools

DANTSYS – 3D deterministic transport theory code DIF3D – 3D deterministic diffusion theory based

computational tool ERANOS code system SCALE code system MCNP(X) – stochastic steady state Monte Carlo computational

code NJOY, TRANSX, CRSRD – nuclear data processing tools NESTLE/PARCS – few-group neutron and hydro-mechanic

codes MICROSHIELD, VISIPLAN, GOLDSYM, radiation shielding

and dose assessment codes MCAM – Monte Carlo Modeling interface program

FEI STU


2014 15

SAFETY Control Systems

Studies of the effectiveness of available control rod designs for GFR2400

Reactivity worth Integral characteristics amplification and interferences

Proposal of heterogeneous CR design Optimal pin radius and position Material composition Utilization of neutron absorber as a part of CR

design

Application of deterministic approaches Covariance matrices of CR amplification factors

FEI STU


2014 16

SAFETY Control Systems 2 Reactivity management by introducing a movable

reflector Localization of local hot spots areas, local multiplication

factors › 1 To flatten the neutron flux distribution by reflector

removal Investigation of various reflector S/As and ring

configuration

Possibilities of third level control system

FEI STU


2014 17

Coupled neutron and Thermal-hydraulics - Kinetic calculations

Processing of nuclear data to few group macro sets Evaluation of reactivity effects of steady state

calculations Conjunction uncertainties (sources of uncertainties) of

investigated parameters to transient calculation Verification of the achieved results by the means of

experimental data Be able to truly predict the kinetic behavior of the

investigated system Based on experience, proceed from kinetics to

dynamics

FEI STU


2014 18

Coupled neutron and Thermal-hydraulic - Kinetic calculations 2

VR-1 Training/academic reactor of CTU in Prague Pool type, square lattice and zero power Thermal neutron spectrum

LR-0 Research reactor operated by Research Centre

Řež Pool type, triangular lattice and zero power Thermal neutron spectrum In the frame of cooperation with these institutes

parallel effort will be made with focus to validate our methods and improve our skills in determining the calculation bias, uncertainties, reactivity feedback effects and other important parameters.

FEI STU


2014 19

ALLEGRO

Demonstrator of the GFR 75 MWth thermal power 2010 memorandum of understanding ALLIANCE - EURATOM 2012 FP7 Allegro Implementing Advanced

Nuclear fuel cycle in Central Europe, ALLEGRO design & safety VUJE (Slovakia) Technology related experiments UJV (Czech

Republic) Closed fuel cycle and fuel issues MTA EK

(Hungary) Industrial application of high temperature gases

NCBJ (Poland)

FEI STU


2014 20

Further activities

Neutronic analyses of Gas Cooled Fast Reactor in the frame of APVV 0123-12 project (Slovak Agency for Science a Research) till November 2017

Analyses oriented mostly to GRF 2400 and ALLEGRO

As associated member in GoFastR -cooperation with VÚJE and group of BUTE

Cooperation with CTU (VR1) and CV Řež (LR 0) benchmark testing simulation tools

FEI STU


2014 21

Thank you for your attention!

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