Identification of spent nuclear fuel with multivariate analysis based on database

Jia-Hang Su; Jun Wu; Si-De Hu

doi:10.7498/aps.68.20190107

Journals >Acta Physica Sinica >Volume 68 >Issue 9 >Page 090204-1 > Article

Acta Physica Sinica
Vol. 68, Issue 9, 090204-1 (2019)

Identification of spent nuclear fuel with multivariate analysis based on database

Jia-Hang Su^1、2、*, Jun Wu², and Si-De Hu³

Author Affiliations

¹Graduate School of China Academy of Engineering Physics, Beijing 100088, China

²Center for Strategic Studies, China Academy of Engineering Physics, Beijing 100088, China

³China Academy of Engineering Physics, Beijing 100088, China

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DOI: 10.7498/aps.68.20190107 Cite this Article

Jia-Hang Su, Jun Wu, Si-De Hu. Identification of spent nuclear fuel with multivariate analysis based on database[J]. Acta Physica Sinica, 2019, 68(9): 090204-1 Copy Citation Text

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Fig. 1. Visualization of database in three-dimensional space.数据库在3维空间的可视化处理

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Diagram for Heron’s formula (U stands for unknown sample, A1, A2, B1, B2 stand for known samples).海伦公式示意图(U点为未知样品点, A1, A2, B1, B2为已知样品点)

Fig. 2. Diagram for Heron’s formula (U stands for unknown sample, A₁, A₂, B₁, B₂ stand for known samples). 海伦公式示意图(U点为未知样品点, A₁, A₂, B₁, B₂为已知样品点)

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Fig. 3. The Polynomial fitting of the linear function values of unknown sample 1.对未知样品1的各线性函数值的多项式拟合

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Fig. 4. Comparation of the three multivariate analysis methods.三种多元统计方法的比较

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堆型	初始装料	丰度	燃耗/GWd·tU^－1
PWR	UO₂	2%—4.5%	5—50
PWR	MOX	天然铀, 4%—5%裂变钚	30—50
CANDU	UO₂	0.711%	0.3, 2—8
CANDU	UO₂	1.2%	5—20
LMFBR	MOX	80%的贫化铀(0.2%以下), 12%的Pu-239, 8%的Pu-240	50—100
MAGNOX (HTGR)	UO₂	0.711%	1—10
GCR (HTGR)	UO₂	1%—4%	1—20
HTGR	UO₂	10%—30%	5—30

Table 1. Input parameters for reactor simulation.

未知样品	模拟参数
未知样品	堆型	初始装料	燃耗/GWd·tU^–1
1	PWR	UO₂, 3.2%	23
2	PWR	MOX, 4.7% 裂变钚	38
3	HTGR	UO₂, 18%	27

Table 2. Input parameters for unknown spent nuclear fuel.

未知样品	模拟参数			预测参数			相对误差
未知样品	堆型	初始装料	燃耗/GWd·tU^–1	堆型	初始装料	燃耗/GWd·tU^–1	初始装料	燃耗/GWd·tU^–1
1	PWR	UO₂, 3.2%	23	PWR	3.197%	23.104	0.5%	2.08%
2	PWR	MOX, 4.7%裂变钚	38	PWR	4.686%	38.324	2.78%	6.49%
3	HTGR	UO₂, 18%	27	HTGR	17.855%	27.328	2.91%	6.55%

Table 3.

Result of identification by using factor analysis.

因子分析鉴别结果

未知样品	分类		概率
未知样品	真实	预测	1(PWR UO₂)	2(PWR MOX)	3(CANDU)	4(LMFBR)	5(MAGNOX)	6(GCR)	7(HTGR)
Uk1	1	1	0.9852	0	0.0148	0	0	0	0
Uk2	2	2	0	1	0	0	0	0	0
Uk3	7	7	0	0	0	0	0	0	1

Table 4.

Result for the determination of reactor type.

反应堆类型判断结果

未知样品	模拟参数		因子分析结果		线性判别分析结果
未知样品	初始装料	燃耗/GWd·tU^–1	初始装料	燃耗/GWd·tU^–1	初始装料	燃耗/GWd·tU^–1
1	UO₂, 3.2%	23	3.197%	23.104	3.201%	23.0361
2	MOX, 4.7%裂变钚	38	4.686%	38.324	4.703%	37.9312
3	UO₂,18%	27	17.855%	27.328	18.003%	27.9196

Table 5.

The comparation of the results from discrimination analysis and factor analysis.

线性判别分析与因子分析结果比较

未知样品	模拟参数		因子分析结果		线性判别分析结果		线性回归分析结果
未知样品	初始装料	燃耗/GWd·tU^–1	初始装料	燃耗/GWd·tU^–1	初始装料	燃耗/GWd·tU^–1	初始装料	燃耗/GWd·tU^–1
1	UO₂, 3.2%	23	3.197%	23.104	3.201%	23.0361	3.2005%	23.022
2	MOX, 4.7%裂变钚	38	4.686%	38.324	4.703%	37.9312	4.6993%	38.019
3	UO₂, 18%	27	17.855%	27.328	18.003%	27.9196	18.001%	26.991

Table 6.

Results for the determination of initial enrichment of uranium and burn-up by linear regression analysis.

利用线性回归分析进行初始装料与燃耗的鉴别分析的结果

Jia-Hang Su, Jun Wu, Si-De Hu. Identification of spent nuclear fuel with multivariate analysis based on database[J]. Acta Physica Sinica, 2019, 68(9): 090204-1

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