Propagation of Nuclear Data Uncertainties for PWR Burnup Calculation

Cross Section and Fission Yields Induced Uncertainty in the Vver-440 Burnup Calculation

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4051613 ◽

2021 ◽

Author(s):

Branislav Vrban ◽

Stefan Cerba ◽

Jakub Luley ◽

Filip Osuský ◽

Vladimir Necas

Keyword(s):

Cross Section ◽

Neutron Cross Section ◽

Nuclear Data ◽

Reactor Operation ◽

Precise Estimation ◽

Stochastic Techniques ◽

Core Characteristics ◽

Fission Yields ◽

Operational Data ◽

Burnup Calculation

Abstract The properties of nuclear fuel depend on the actual isotopic composition which develops during a reactor operation. In practice, the prediction accuracy of burnup calculations serves as the basis for the future precise estimation of a core lifetime and other safety-based core characteristics. The present study quantifies nuclear data induced uncertainties of nuclide concentrations and multiplication factors in VVER-440 fuel depletion analysis. The well-known SCALE system and the TRITON sequence are used with the NEWT deterministic solver in the SAMPLER module that implements stochastic techniques to assess the uncertainty in computed results. The propagation of uncertainties in neutron cross section and fission yields is studied through the depletion calculation of 2D heterogeneous VVER-440 fuel assembly with an average enrichment of 4.87 wt % of 235U and six gadolinium rods with 3.35 % of Gd2O3. In the paper, fixed nominal depletion conditions are based on the real operational data of the Slovak NPP Bohunice unit 4 during cycle 30. In total 250 cases with uncertain parameters are computed and the results are evaluated by an auxiliary tool.

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Validation of Correlations Between Nd Isotopes and Difficult-to-Measure Nuclides Predicted With Burn-Up Calculation Code by Postirradiation Examination

ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B ◽

10.1115/icem2011-59086 ◽

2011 ◽

Author(s):

Shiho Asai ◽

Keisuke Okumura ◽

Yukiko Hanzawa ◽

Hideya Suzuki ◽

Masaaki Toshimitsu ◽

...

Keyword(s):

Inductively Coupled Plasma ◽

Nuclear Data ◽

Insoluble Residue ◽

Nd Isotopes ◽

Inductively Coupled ◽

Icp Ms ◽

Nuclear Data Library ◽

Plasma Mass Spectrometry ◽

Calculation Code ◽

Burnup Calculation

Correlations between Nd isotopes and difficult-to-measure (DTM) nuclides, such as Se-79, Tc-99, Sn-126, and Cs-135, predicted using a calculation code have been validated by postirradiation examination (PIE). The calculation was performed with a burnup calculation code, MVP-BURN, using the updated nuclear data library JENDL-4.0. An irradiated PWR fuel with a burnup of 44.9 GWd/t and a cooling time of 7458 days was used as a standard sample. The concentrations of Nd isotopes in the sample solutions were determined by inductively coupled plasma mass spectrometry (ICP-MS) after purification by two consecutive anion-exchange separations. The ratios of Se-79 and Cs-135 to Nd isotopes (Nd-145, Nd-146, and Nd-145+Nd-146) calculated using MVP-BURN were in good agreement with PIE values within the deviations of 8% and 6%, respectively. This indicates that these calculated ratios are applicable to the scaling factors of Se-79 and Cs-135. For Tc-99 and Sn-126, the calculated values were respectively about 50% and 20% higher than the PIE values. These overestimations were mainly caused by the lack of the contribution of an insoluble residue to the measured concentrations.

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Comparison of Burnup Calculation Results Using Several Evaluated Nuclear Data Files

Journal of Nuclear Science and Technology ◽

10.1080/18811248.2002.9715160 ◽

2002 ◽

Vol 39 (1) ◽

pp. 82-89 ◽

Cited By ~ 3

Author(s):

Kenya SUYAMA ◽

Jun-ichi KATAKURA ◽

Takehide KIYOSUMI ◽

Toshiyuki KANEKO ◽

Yasushi NOMURA

Keyword(s):

Nuclear Data ◽

Calculation Results ◽

Data Files ◽

Evaluated Nuclear Data ◽

Burnup Calculation

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FISSION YIELD UNCERTAINTY PROPAGATION IN MULTI-PASS REFUELING PEBBLE-BED HTGR

EPJ Web of Conferences ◽

10.1051/epjconf/202124715006 ◽

2021 ◽

Vol 247 ◽

pp. 15006

Author(s):

Yizhen Wang ◽

Menglei Cui ◽

Jiong Guo ◽

Fu Li

Keyword(s):

Fission Product ◽

Sampling Method ◽

Uncertainty Propagation ◽

Product Yield ◽

Nuclear Data ◽

Fission Yield ◽

Pebble Bed ◽

Stochastic Sampling ◽

Fission Product Yield ◽

Burnup Calculation

Multi-pass refueling scheme is a highlighted feature of pebble bed HTGR which spatially mixes the burnup calculation inside core. Such refueling scheme relate burnup calculation in one region of the core to others and thus affects the uncertainty propagation of nuclear data, e.g. fission product yield. In this work, thermal neutron induced U-235 fission product yield uncertainties are propagated in HTR-PM models with various refueling schemes in V.S.O.P. code. And the effect of multi-pass refueling scheme is studied. Bayesian method is applied to estimate the covariance of fission product yield based on ENDF/B-VII.1 fission yield sub-library. Uncertainty quantification is performed with stochastic sampling method and log-normal based correlated sampling method is used to generate reasonable and self-consistent fission product yield samples. The analyzed results indicate that multi-pass refueling scheme could affect the uncertainty propagation of reactor local responses.

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