for MYRRHA using a Monte Carlo techniqueIwamoto, Hiroki 
; Stankovskiy, A.*; Fiorito, L.*; Van den Eynde, G.*
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neutron fraction for critical and subcritical cores of the MYRRHA reactor using the continuous-energy Monte Carlo transport code MCNP. The sensitivities are calculated by the modified 
-ratio method proposed by Chiba. Comparing the sensitivities obtained with different scaling factors 
introduced by Chiba shows that a value of 
is the most suitable for the uncertainty quantification of . Using the calculated sensitivities and the JENDL-4.0u covariance data, the uncertainties for the critical and subcritical cores are determined to be 2.2 
0.2% and 2.0 0.2%, respectively, which are dominated by delayed neutron yield of 
Pu and 
U.
Language |
: | English |
|---|---|---|
Journal |
: | |
Volume |
: | 4 |
Number |
: | |
Pages |
: | p.42_1 - 42_7 |
Publication Year/Month |
: | 2018/11 |
Meeting title |
: | 4th International Workshop on Nuclear Data Covariances (CW 2017) |
Held date |
: | 2017/10 |
Location (city) |
: | Aix-en-Province |
Location (country) |
: | France |
Paper URL |
: |
|
Keywords |
: | Effective Delayed Neutron Fraction; Sensitivity Analysis; Uncertainty Analysis; MCNP; JENDL-4.0 |
Accesses |
: |
- Accesses |
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Altmetrics |
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