Accounting for Changing Source Distributions in Light Water Reactor Surveillance Dosimetry Analysis

Maerker, R.E.; Williams, Mark L.; Broadhead, B.L.

doi:10.13182/nse86-a18342

Cited by 6 publications

(3 citation statements)

References 2 publications

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“…However, changes due to other design aspects (i.e. reflector cooling channels) could alter results, but the current margin indicates that expected design changes will 03004-p. 7 EPJ Web of Conferences likely uphold acceptable levels. Future work will involve implementing an accurate representation of the spatial and temporal source distribution [21] in order to quantify different key radiation parameters as they accumulate in integral components within the pressure vessel throughout the lifetime of the I 2 S-LWR.…”

Section: Discussionmentioning

confidence: 99%

“…A fission source distribution and spectrum over the full lifetime of a reactor [7] can be difficult to quantify, since it requires full-core depletion through multiple batches moving towards an equilibrium fuel cycle and predicting the future reloading strategy for the 100-year operating lifetime. Since the goal of this study was to perform a scaling analysis of neutron fluence to the RPV with respect to different parameters, a more simplified approach was used which would envelope maximum and minimum bounds.…”

Section: Introductionmentioning

confidence: 99%

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Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I²S-LWR)

Flaspoehler

Petrović

2016

EPJ Web of Conferences

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Abstract. One of the major limiting factors to nuclear reactors lifetime is the radiationinduced material damage in the Reactor Pressure Vessel (RPV). While older reactors were designed assuming a 40-year operating lifetime, new reactor designs are expected to have lifetimes up to 100 years. For safe operation, the integrity of the RPV must be ensured against significant material property changes. In this work, typical neutron damage indicators are calculated in the RPV of the I 2 S-LWR (Integral Inherently Safe LWR) Power Plant, including DPA (displacements per atom) and fast neutron fluence (>1 MeV and >0.1MeV). I 2 S-LWR is a PWR of integral design, which means that its wider downcomer provides additional shielding to the vessel. However, its higher core power density and longer lifetime may offset this advantage. In order to accurately represent the neutron environment for RPV damage assessment, a detailed model based on the preliminary design specifications of the I 2 S-LWR was developed to be used in the MAVRIC (Monaco with Automated Variance Reduction using Importance Calculations) sequence of the Scale6.1 code package. MAVRIC uses the CADIS (Consistent Adjoint-Driven Importance Sampling) methodology to bias a fixed-source MC (Monte Carlo) simulation. To establish the upper limit of a bounding envelope, a flat-source distribution was used. For the low limit, a centerpeaked source was generated using the KENO-VI criticality sequence assuming uniform fresh fuel core. Results based on the preliminary I 2 S-LWR model show that DPA rates and fast fluence rates are conservatively 75% lower than in typical PWRs being operated currently in the US.

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I²S-LWR)

Flaspoehler

Petrović

2016

EPJ Web of Conferences

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“…The method chosen for the calculations is a modification of a fiuence-rate synthesis procedure often used in more conventional geometry (3,4). By decomposing the usual synthesis prescription into two components, one contribution arising from sources (A) lying above the PLSA region and the other from sources (B) lying within the levels defined by the PLSA region, one can write the superposition-synthesis equation as…”

Section: Description Of the Calculationsmentioning

confidence: 99%

Analysis of the Venus-3 Experiments

Maerker¹,

D'hondt²,

Leenders³

et al. 1992

Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry

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The results of applying a hybrid superpositionsynthesis calculational method to a mockup of a threedimensional geometry involving a partial length shield assembly at the VENUS-3 facility in Mol, Belgium, are described. Comparisons of transport calculations using the method and many measurements involving nickel, indium, and aluminum dosimeters indicate agreement usually to within measurement uncertainties estimated at around 5%, if effects of inaccuracies in the dosimeter cross sections are minimized and proper orientation of the coordinate system used in the synthesis procedure is observed. These conclusions suggest a solution to the problem of predicting pressure vessel fluence in reactors modified by these partial-length shield assemblies may already exist.

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Verification of multilevel octree grid algorithm of S transport calculation with the Balakovo-3 VVER-1000 neutron dosimetry benchmark

Liu

Zhang²,

Wei³

et al. 2023

Nuclear Engineering and Technology

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Accounting for Changing Source Distributions in Light Water Reactor Surveillance Dosimetry Analysis

Cited by 6 publications

References 2 publications

Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I²S-LWR)

Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I²S-LWR)

Analysis of the Venus-3 Experiments

Verification of multilevel octree grid algorithm of S transport calculation with the Balakovo-3 VVER-1000 neutron dosimetry benchmark

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Accounting for Changing Source Distributions in Light Water Reactor Surveillance Dosimetry Analysis

Cited by 6 publications

References 2 publications

Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I2S-LWR)

Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I2S-LWR)

Analysis of the Venus-3 Experiments

Verification of multilevel octree grid algorithm of S transport calculation with the Balakovo-3 VVER-1000 neutron dosimetry benchmark

Contact Info

Product

Resources

About

Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I²S-LWR)

Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I²S-LWR)