[논문]Verification of Graphite Isotope Ratio Method Combined With Polynomial Regression for the Estimation of Cumulative Plutonium Production in a Graphite-Moderated Reactor

Kim, Kyeongwon; Han, Jinseok; Lee, Hyun Chul; Jang, Junkyung; Lee, Deokjung

doi:10.7733/jnfcwt.2021.037

Verification of Graphite Isotope Ratio Method Combined With Polynomial Regression for the Estimation of Cumulative Plutonium Production in a Graphite-Moderated Reactor 원문보기

Journal of nuclear fuel cycle and waste technology = 방사성폐기물학회지, v.19 no.4, 2021년, pp.447 - 457

Kim, Kyeongwon (Ulsan National Institute of Science and Technology) , Han, Jinseok (Pusan National University) , Lee, Hyun Chul (Pusan National University) , Jang, Junkyung (Pusan National University) , Lee, Deokjung (Ulsan National Institute of Science and Technology)

Abstract ▼ AI-Helper

Graphite Isotope Ratio Method (GIRM) can be used to estimate plutonium production in a graphite-moderated reactor. This study presents verification results for the GIRM combined with a 3-D polynomial regression function to estimate cumulative plutonium production in a graphite-moderated reactor. Using the 3-D Monte-Carlo method, verification was done by comparing the cumulative plutonium production with the GIRM. The GIRM can estimate plutonium production for specific sampling points using a function that is based on an isotope ratio of impurity elements. In this study, the 10B/11B isotope ratio was chosen and calculated for sampling points. Then, 3-D polynomial regression was used to derive a function that represents a whole core cumulative plutonium production map. To verify the accuracy of the GIRM with polynomial regression, the reference value of plutonium production was calculated using a Monte-Carlo code, MCS, up to 4250 days of depletion. Moreover, the amount of plutonium produced in certain axial layers and fuel pins at 1250, 2250, and 3250 days of depletion was obtained and used for additional verification. As a result, the difference in the total cumulative plutonium production based on the MCS and GIRM results was found below 3.1% with regard to the root mean square (RMS) error.

주제어

표/그림 (19)

그림 Fig. 1. Radial and axial layout of Calder Hall reactor.
그림 Fig. 2. Geometry of fuel pin for Zone A.
표 Table 1. Design parameters of Calder Hall reactor
그림 Fig. 4. Cumulative plutonium production for the Calder Hall reactor.
그림 Fig. 3. Effective multiplication factors of whole core.
표 Table 2. Effective multiplication factors of whole core
표 Table 3. Cumulative plutonium isotopes production in Calder Hall reactor at burnup steps
그림 Fig. 5. Plutonium isotopes mass density for the ¹⁰B/¹¹B ratio in a 2-D fuel pin.
그림 Fig. 6. Radial and axial sampling points.
그림 Fig. 7. Comparison of the cumulative plutonium production with different orders of regression.
그림 Fig. 8. Comparison of total cumulative plutonium production calculated by MCS and GIRM.
표 Table 4. Comparison of total cumulative plutonium production calculated by MCS and GIRM
표 Table 5. Comparison of axial cumulative plutonium production calculated by MCS and GIRM at a burnup step of 1250 day
표 Table 6. Comparison of axial cumulative plutonium production calculated by MCS and GIRM at a burnup step of 2250 day
그림 Fig. 9. Fuel pin index for pin-wise comparison of plutonium production.
표 Table 7. Comparison of axial cumulative plutonium production calculated by MCS and GIRM at a burnup of 3250 day
표 Table 8. Comparison of pin-wise cumulative plutonium production calculated by MCS and GIRM at a burnup step of 1250 day
표 Table 9. Comparison of pin-wise cumulative plutonium production calculated by MCS and GIRM at a burnup step of 2250 day
표 Table 10. Comparison of pin-wise cumulative plutonium production calculated by MCS and GIRM at a burnup step of 3250 day

참고문헌 (7)

J.P. McNeece, B.D. Reid, and T.W. Wood. The Graphite Isotope Ratio Method (GIRM): A Plutonium Production Verification Tool, Pacific Northwest National Laboratory Technical Report, PNNL-12095 (1999).
B.D. Reid, W.C. Morgan, E.F. Love, Jr, D.C. Gerlach, S.L. Petersen, J.V. Livingston, L.R. Greenwood, and J.P. McNeece. Graphite Isotope Ratio Method Development Report: Irradiation Test Demonstration of Uranium as a Low Fluence Indicator, Pacific Northwest National Laboratory Technical Report, PNNL-13056 (1999).
J. Han, J. Jang, and H.C. Lee, "A Suitability Study on the Indicator Isotope for Graphite Isotope Ratio Method (GIRM)", J. Nucl. Fuel Cycle Waste Technol., 18(1), 83-90 (2020).

원문보기 상세보기
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상세보기
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상세보기
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