We found a match
Your institution may have access to this item. Find your institution then sign in to continue.
- Title
无源符合中子计数器探测效率与 泄漏增殖系数的模拟计算.
- Authors
初泉丽; 李多宏; 陆宏; 鲍家斌; 张天宝; 田川; 胡洪涛; 杨丽芳
- Abstract
The passive coincidence neutron method is usually used to determine the mass of plutonium spontaneously fission in the measured source term. It needs to conduct comprehensive and in-depth research and calculation on key parameters, such as detection efficiency and leakage multiplication coefficient, and then count the detected coincidence neutrons and calculate the plutonium content using relevant formulas. In this paper, while simulating the efficiency of the detector, 252Cf standard source was used as the measurement sample, and the spontaneous fission neutron energy spectrum was close to the pure fission spectrum. Therefore, it is suitable for passive measurement of fast neutrons, that is, on the basis of active measurement of fast neutrons, the Am-Li neutron source is removed, and the structures such as polyethylene moderator and cadmium liner are retained; while simulating the leakage multiplication coefficient M, the detector model in the MCNP input card is the same as the active measurement of fast neutrons model used to simulate the detector efficiency, which has no impact on the accuracy of the results. In order to obtain the detection efficiency and leakage multiplication coefficient of the coincidence neutron counter, the MCNP automatic modeling function for the AWCC neutron counter was realized by writing a script in MATLAB. The MCNP input file of the AWCC neutron counter can be quickly produced only by inputting structural parameters, and the simulation of the AWCC neutron counter with the same structure and different sizes can be realized to carry out the detector efficiency calculation of reaction rate between neutron and 3 He and leakage multiplication coefficient M in measurement of waste containing Pu. The theoretical detection efficiency was 24%, and the detector efficiency calculated by this simulation was 23.27%. There is little difference between the two results, so it can be judged that the reliability of the simulation results is high. The calculation results of the leakage multiplication coefficient M increase with the increase of the material quality, which is consistent with the change trend of the results in reference[4]. This work will lay a theoretical foundation for the practical application of the detector.
- Subjects
NEUTRON measurement; COINCIDENCE circuits; FAST neutrons; NEUTRON temperature; LEAK detection; NEUTRON counters
- Publication
World Nuclear Geoscience, 2022, Vol 39, Issue 3, p596
- ISSN
1672-0636
- Publication type
Article
- DOI
10.3969/j.issn.1672-0636.2022.03.022