<trans-title xml:lang="en">Identification of spent nuclear fuel with multivariate analysis based on database</trans-title>

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 2. Input parameters for unknown spent nuclear fuel.
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Table 2. Input parameters for unknown spent nuclear fuel.
未知样品模拟参数
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 3.
Result of identification by using factor analysis.
因子分析鉴别结果

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Table 3.
Result of identification by using factor analysis.
因子分析鉴别结果

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 4.
Result for the determination of reactor type.
反应堆类型判断结果
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Table 4.
Result for the determination of reactor type.
反应堆类型判断结果
未知样品分类概率
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 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

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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
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 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

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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

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

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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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Paper Information

Category:

Received: Jan. 21, 2019

Accepted: --

Published Online: Oct. 29, 2019

The Author Email:

DOI:10.7498/aps.68.20190107

Topics

Nuclear physics

Particles and fields

Particle and nuclear astrophysics and cosmology

Table 1. Input parameters for reactor simulation.

Table 1. Input parameters for reactor simulation.

Table 2. Input parameters for unknown spent nuclear fuel.

Table 2. Input parameters for unknown spent nuclear fuel.

Table 3. Result of identification by using factor analysis.因子分析鉴别结果

Table 3. Result of identification by using factor analysis.因子分析鉴别结果

Table 4. Result for the determination of reactor type.反应堆类型判断结果

Table 4. Result for the determination of reactor type.反应堆类型判断结果

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

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

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

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

Table 3.
Result of identification by using factor analysis.
因子分析鉴别结果

Table 3.
Result of identification by using factor analysis.
因子分析鉴别结果

Table 4.
Result for the determination of reactor type.
反应堆类型判断结果

Table 4.
Result for the determination of reactor type.
反应堆类型判断结果

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

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

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

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