Validation of MCBEND dosimetry predictions against measurements from Hunterston B advanced gas-cooled reactor

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

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Validation of MCBEND dosimetry predictions against measurements from Hunterston B advanced gas-cooled reactor. / Allen, Dennis ; Thornton, Dean A.; Shaw, Simon E.; Wagemans, Jan; Whiley, Geoff S.; Watson, James D.; Huggon, Adrian P.; Mason, Paolo.

American Society for Testing and Materials Selected Technical Papers: Reactor dosimetry: 16th international symposium. Vol. STP1608 2018. ed. 2018. p. 212-226 STP160820170052 (Journal of ASTM International).

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Harvard

Allen, D, Thornton, DA, Shaw, SE, Wagemans, J, Whiley, GS, Watson, JD, Huggon, AP & Mason, P 2018, Validation of MCBEND dosimetry predictions against measurements from Hunterston B advanced gas-cooled reactor. in American Society for Testing and Materials Selected Technical Papers: Reactor dosimetry: 16th international symposium. 2018 edn, vol. STP1608, STP160820170052, Journal of ASTM International, pp. 212-226, 2017 - 16th International Symposium on Reactor Dosimetry, Santa Fee, United States, 2017-05-07. https://doi.org/10.1520/STP160820170052

APA

Allen, D., Thornton, D. A., Shaw, S. E., Wagemans, J., Whiley, G. S., Watson, J. D., ... Mason, P. (2018). Validation of MCBEND dosimetry predictions against measurements from Hunterston B advanced gas-cooled reactor. In American Society for Testing and Materials Selected Technical Papers: Reactor dosimetry: 16th international symposium (2018 ed., Vol. STP1608, pp. 212-226). [STP160820170052] (Journal of ASTM International). https://doi.org/10.1520/STP160820170052

Vancouver

Allen D, Thornton DA, Shaw SE, Wagemans J, Whiley GS, Watson JD et al. Validation of MCBEND dosimetry predictions against measurements from Hunterston B advanced gas-cooled reactor. In American Society for Testing and Materials Selected Technical Papers: Reactor dosimetry: 16th international symposium. 2018 ed. Vol. STP1608. 2018. p. 212-226. STP160820170052. (Journal of ASTM International). https://doi.org/10.1520/STP160820170052

Author

Allen, Dennis ; Thornton, Dean A. ; Shaw, Simon E. ; Wagemans, Jan ; Whiley, Geoff S. ; Watson, James D. ; Huggon, Adrian P. ; Mason, Paolo. / Validation of MCBEND dosimetry predictions against measurements from Hunterston B advanced gas-cooled reactor. American Society for Testing and Materials Selected Technical Papers: Reactor dosimetry: 16th international symposium. Vol. STP1608 2018. ed. 2018. pp. 212-226 (Journal of ASTM International).

Bibtex - Download

@inproceedings{2dd944addf29413e88a665e0cabce2ef,
title = "Validation of MCBEND dosimetry predictions against measurements from Hunterston B advanced gas-cooled reactor",
abstract = "The core restraints of advanced gas-cooled reactors are important structural components necessary for maintaining the geometric integrity of the cores. Neutron damage and nuclear heating rates, calculated using the Monte Carlo code MCBEND, have underpinned the safety case for continued operation of four reactors. To validate these calculations, neutron activation measurements were commissioned. A neutron flux activation “stringer” was deployed in the graphite side reflector of one of the Hunterston B reactors and irradiated for a period of approximately three years. A capsule attached to the bottom end of this cable contained a range of fast and thermal neutron activation monitor wires to provide additional spectral information. Following its successful withdrawal, measurements were undertaken at SCK-CEN’s laboratory in Mol, Belgium, to provide monitor wire activities. In parallel with this, activation calculations were undertaken by Amec Foster Wheeler using a MCBEND model tailored to the state of the reactor during the irradiation period. Time-varying neutron source data were used, decay-adjusted for the half-lives of the activation monitors, in order to accommodate the effects upon the expected activities of time-varying reactor power. Adjustments were made for neutron flux attenuation within the stringer capsule and cable and, where necessary, corrections were also made for parent and activation nuclide burnout. There was no requirement for spectral adjustment. Excellent agreement between calculated and measured activities was obtained for both fast and thermal neutron responses; the overall calculated/measured ratios were 1.14 ± 0.15 and 1.11 ± 0.12, respectively. These are sufficiently close to the desired value of unity to provide confidence in the ability of the calculation route to predict neutron damage rates within the core restraint components. This successful validation supports the case for life extension of the Hunterston B and Hinkley Point B power plants.",
keywords = "MCBEND, Advanced Gas-cooled Reactor (AGR), validation, neutron flux measurement, reactor dosimetry, Monte Carlo",
author = "Dennis Allen and Thornton, {Dean A.} and Shaw, {Simon E.} and Jan Wagemans and Whiley, {Geoff S.} and Watson, {James D.} and Huggon, {Adrian P.} and Paolo Mason",
note = "Score=3",
year = "2018",
month = "8",
day = "1",
doi = "10.1520/STP160820170052",
language = "English",
volume = "STP1608",
series = "Journal of ASTM International",
publisher = "ASTM International",
pages = "212--226",
booktitle = "American Society for Testing and Materials Selected Technical Papers",
edition = "2018",

}

RIS - Download

TY - GEN

T1 - Validation of MCBEND dosimetry predictions against measurements from Hunterston B advanced gas-cooled reactor

AU - Allen, Dennis

AU - Thornton, Dean A.

AU - Shaw, Simon E.

AU - Wagemans, Jan

AU - Whiley, Geoff S.

AU - Watson, James D.

AU - Huggon, Adrian P.

AU - Mason, Paolo

N1 - Score=3

PY - 2018/8/1

Y1 - 2018/8/1

N2 - The core restraints of advanced gas-cooled reactors are important structural components necessary for maintaining the geometric integrity of the cores. Neutron damage and nuclear heating rates, calculated using the Monte Carlo code MCBEND, have underpinned the safety case for continued operation of four reactors. To validate these calculations, neutron activation measurements were commissioned. A neutron flux activation “stringer” was deployed in the graphite side reflector of one of the Hunterston B reactors and irradiated for a period of approximately three years. A capsule attached to the bottom end of this cable contained a range of fast and thermal neutron activation monitor wires to provide additional spectral information. Following its successful withdrawal, measurements were undertaken at SCK-CEN’s laboratory in Mol, Belgium, to provide monitor wire activities. In parallel with this, activation calculations were undertaken by Amec Foster Wheeler using a MCBEND model tailored to the state of the reactor during the irradiation period. Time-varying neutron source data were used, decay-adjusted for the half-lives of the activation monitors, in order to accommodate the effects upon the expected activities of time-varying reactor power. Adjustments were made for neutron flux attenuation within the stringer capsule and cable and, where necessary, corrections were also made for parent and activation nuclide burnout. There was no requirement for spectral adjustment. Excellent agreement between calculated and measured activities was obtained for both fast and thermal neutron responses; the overall calculated/measured ratios were 1.14 ± 0.15 and 1.11 ± 0.12, respectively. These are sufficiently close to the desired value of unity to provide confidence in the ability of the calculation route to predict neutron damage rates within the core restraint components. This successful validation supports the case for life extension of the Hunterston B and Hinkley Point B power plants.

AB - The core restraints of advanced gas-cooled reactors are important structural components necessary for maintaining the geometric integrity of the cores. Neutron damage and nuclear heating rates, calculated using the Monte Carlo code MCBEND, have underpinned the safety case for continued operation of four reactors. To validate these calculations, neutron activation measurements were commissioned. A neutron flux activation “stringer” was deployed in the graphite side reflector of one of the Hunterston B reactors and irradiated for a period of approximately three years. A capsule attached to the bottom end of this cable contained a range of fast and thermal neutron activation monitor wires to provide additional spectral information. Following its successful withdrawal, measurements were undertaken at SCK-CEN’s laboratory in Mol, Belgium, to provide monitor wire activities. In parallel with this, activation calculations were undertaken by Amec Foster Wheeler using a MCBEND model tailored to the state of the reactor during the irradiation period. Time-varying neutron source data were used, decay-adjusted for the half-lives of the activation monitors, in order to accommodate the effects upon the expected activities of time-varying reactor power. Adjustments were made for neutron flux attenuation within the stringer capsule and cable and, where necessary, corrections were also made for parent and activation nuclide burnout. There was no requirement for spectral adjustment. Excellent agreement between calculated and measured activities was obtained for both fast and thermal neutron responses; the overall calculated/measured ratios were 1.14 ± 0.15 and 1.11 ± 0.12, respectively. These are sufficiently close to the desired value of unity to provide confidence in the ability of the calculation route to predict neutron damage rates within the core restraint components. This successful validation supports the case for life extension of the Hunterston B and Hinkley Point B power plants.

KW - MCBEND

KW - Advanced Gas-cooled Reactor (AGR)

KW - validation

KW - neutron flux measurement

KW - reactor dosimetry

KW - Monte Carlo

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/34696142

U2 - 10.1520/STP160820170052

DO - 10.1520/STP160820170052

M3 - In-proceedings paper

VL - STP1608

T3 - Journal of ASTM International

SP - 212

EP - 226

BT - American Society for Testing and Materials Selected Technical Papers

ER -

ID: 6776447