# Application of GRS method to evaluation of uncertainties of calculation parameters of perspective sodium-cooled fast reactor

## Abstract

A number of recent studies have been devoted to the estimation of errors of reactor calculation parameters by the GRS (Generation Random Sampled) method. This method is based on direct sampling input data resulting in formation of random sets of input parameters which are used for multiple calculations. Once these calculations are performed, statistical processing of the calculation results is carried out to determine the mean value and the variance of each calculation parameter of interest. In our study this method is used for estimation of errors of calculation parameters (K{sub eff}, power density, dose rate) of a perspective sodium-cooled fast reactor. Neutron transport calculations were performed by the nodal diffusion code TRIGEX and Monte Carlo code MMK. (authors)

- Authors:

- Inst. for Physics and Power Engineering, Bondarenko Square 1, Obninsk 244033, Kaluga Region (Russian Federation)

- Publication Date:

- Research Org.:
- American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)

- OSTI Identifier:
- 22105875

- Resource Type:
- Conference

- Resource Relation:
- Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 7 refs.

- Country of Publication:
- United States

- Language:
- English

- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 97 MATHEMATICAL METHODS AND COMPUTING; COMPUTER CALCULATIONS; DATA COVARIANCES; DOSE RATES; ERRORS; EVALUATION; FAST REACTORS; MONTE CARLO METHOD; NEUTRON TRANSPORT; POWER DENSITY; RANDOMNESS; SODIUM; SODIUM COOLED REACTORS; STATISTICS

### Citation Formats

```
Peregudov, A., Andrianova, O., Raskach, K., and Tsibulya, A.
```*Application of GRS method to evaluation of uncertainties of calculation parameters of perspective sodium-cooled fast reactor*. United States: N. p., 2012.
Web.

```
Peregudov, A., Andrianova, O., Raskach, K., & Tsibulya, A.
```*Application of GRS method to evaluation of uncertainties of calculation parameters of perspective sodium-cooled fast reactor*. United States.

```
Peregudov, A., Andrianova, O., Raskach, K., and Tsibulya, A. Sun .
"Application of GRS method to evaluation of uncertainties of calculation parameters of perspective sodium-cooled fast reactor". United States.
```

```
@article{osti_22105875,
```

title = {Application of GRS method to evaluation of uncertainties of calculation parameters of perspective sodium-cooled fast reactor},

author = {Peregudov, A. and Andrianova, O. and Raskach, K. and Tsibulya, A.},

abstractNote = {A number of recent studies have been devoted to the estimation of errors of reactor calculation parameters by the GRS (Generation Random Sampled) method. This method is based on direct sampling input data resulting in formation of random sets of input parameters which are used for multiple calculations. Once these calculations are performed, statistical processing of the calculation results is carried out to determine the mean value and the variance of each calculation parameter of interest. In our study this method is used for estimation of errors of calculation parameters (K{sub eff}, power density, dose rate) of a perspective sodium-cooled fast reactor. Neutron transport calculations were performed by the nodal diffusion code TRIGEX and Monte Carlo code MMK. (authors)},

doi = {},

journal = {},

number = ,

volume = ,

place = {United States},

year = {2012},

month = {7}

}