Abstract
As the strategy for DUPIC(Direct Use of spent PWR fuel In CANDU reactor) process safeguards, the neutron detection method was introduced to account for nuclear materials in the whole DUPIC process by selectively measuring spontaneous fission neutron signals from {sup 244}Cm. DSNC was designed and manufactured to measure the account of curium in the fuel bundle and associated process samples in the DUPIC fuel cycle. The MCNP code had response profile along the length of the CANDU type fuel bundle. It was found experimentally that the output signal variation due to the overall azimuthal asymmetry was less than 0.2%. The longitudinal detection efficiency distribution at every position including both ends was kept less than 2% from the average value. Spent fuel standards almost similar to DUPIC process material were fabricated from a single spent PWR fuel rod and the performance verification of the DSNC is in progress under very high radiation environment. The results of this test will be eventually benchmarked with other sources such as code simulation, chemical analysis and gamma analysis. COREMAS-DUPIC has been developed for the accountability management of nuclear materials treated by DUPIC facility. This system is able to track the controlled nuclear materials maintaining the
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Hong, J S;
Kim, H D;
Lee, Y G;
Kang, H Y;
Cha, H R;
Byeon, K H;
Park, Y S;
Choi, H N
[1]
- Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Citation Formats
Hong, J S, Kim, H D, Lee, Y G, Kang, H Y, Cha, H R, Byeon, K H, Park, Y S, and Choi, H N.
Technology development for DUPIC process safeguards.
Korea, Republic of: N. p.,
1997.
Web.
Hong, J S, Kim, H D, Lee, Y G, Kang, H Y, Cha, H R, Byeon, K H, Park, Y S, & Choi, H N.
Technology development for DUPIC process safeguards.
Korea, Republic of.
Hong, J S, Kim, H D, Lee, Y G, Kang, H Y, Cha, H R, Byeon, K H, Park, Y S, and Choi, H N.
1997.
"Technology development for DUPIC process safeguards."
Korea, Republic of.
@misc{etde_601100,
title = {Technology development for DUPIC process safeguards}
author = {Hong, J S, Kim, H D, Lee, Y G, Kang, H Y, Cha, H R, Byeon, K H, Park, Y S, and Choi, H N}
abstractNote = {As the strategy for DUPIC(Direct Use of spent PWR fuel In CANDU reactor) process safeguards, the neutron detection method was introduced to account for nuclear materials in the whole DUPIC process by selectively measuring spontaneous fission neutron signals from {sup 244}Cm. DSNC was designed and manufactured to measure the account of curium in the fuel bundle and associated process samples in the DUPIC fuel cycle. The MCNP code had response profile along the length of the CANDU type fuel bundle. It was found experimentally that the output signal variation due to the overall azimuthal asymmetry was less than 0.2%. The longitudinal detection efficiency distribution at every position including both ends was kept less than 2% from the average value. Spent fuel standards almost similar to DUPIC process material were fabricated from a single spent PWR fuel rod and the performance verification of the DSNC is in progress under very high radiation environment. The results of this test will be eventually benchmarked with other sources such as code simulation, chemical analysis and gamma analysis. COREMAS-DUPIC has been developed for the accountability management of nuclear materials treated by DUPIC facility. This system is able to track the controlled nuclear materials maintaining the material inventory in near-real time and to generate the required material accountability records and reports. Concerning the containment and surveillance technology, a focused R and D effort is given to the development of unattended continuous monitoring system. Currently, the component technologies of radiation monitoring and surveillance have been established, and continued R and D efforts are given to the integration of the components into automatic safeguards diagnostics. (author).}
place = {Korea, Republic of}
year = {1997}
month = {Jul}
}
title = {Technology development for DUPIC process safeguards}
author = {Hong, J S, Kim, H D, Lee, Y G, Kang, H Y, Cha, H R, Byeon, K H, Park, Y S, and Choi, H N}
abstractNote = {As the strategy for DUPIC(Direct Use of spent PWR fuel In CANDU reactor) process safeguards, the neutron detection method was introduced to account for nuclear materials in the whole DUPIC process by selectively measuring spontaneous fission neutron signals from {sup 244}Cm. DSNC was designed and manufactured to measure the account of curium in the fuel bundle and associated process samples in the DUPIC fuel cycle. The MCNP code had response profile along the length of the CANDU type fuel bundle. It was found experimentally that the output signal variation due to the overall azimuthal asymmetry was less than 0.2%. The longitudinal detection efficiency distribution at every position including both ends was kept less than 2% from the average value. Spent fuel standards almost similar to DUPIC process material were fabricated from a single spent PWR fuel rod and the performance verification of the DSNC is in progress under very high radiation environment. The results of this test will be eventually benchmarked with other sources such as code simulation, chemical analysis and gamma analysis. COREMAS-DUPIC has been developed for the accountability management of nuclear materials treated by DUPIC facility. This system is able to track the controlled nuclear materials maintaining the material inventory in near-real time and to generate the required material accountability records and reports. Concerning the containment and surveillance technology, a focused R and D effort is given to the development of unattended continuous monitoring system. Currently, the component technologies of radiation monitoring and surveillance have been established, and continued R and D efforts are given to the integration of the components into automatic safeguards diagnostics. (author).}
place = {Korea, Republic of}
year = {1997}
month = {Jul}
}