CENDL-3.2与ENDF/B-Ⅷ.0的<sup>56</sup>Fe评价截面对屏蔽计算影响研究

张斌; 马续波; 胡馗; 陈义学; 吴海成

doi:10.13832/j.jnpe.2022.01.0057

CENDL-3.2与ENDF/B-Ⅷ.0的⁵⁶Fe评价截面对屏蔽计算影响研究

doi: 10.13832/j.jnpe.2022.01.0057

张斌^1,,
马续波^1, ,,
胡馗¹,
陈义学¹,
吴海成²

1.
华北电力大学核科学与工程学院，北京，102206
2.
中国原子能科学研究院核数据重点实验室，北京，102413

基金项目: 国家自然科学基金项目（11875128）

详细信息

作者简介:
张　斌（1995—），男，博士，现主要从事核数据方面的研究，E-mail: wenwubingo@163.com

通讯作者:
马续波，E-mail: maxb917@163.com

中图分类号: TL328；TL329⁺.3；TL341
计量
- 文章访问数: 231
- HTML全文浏览量: 132
- PDF下载量: 34
- 被引次数: 0
出版历程
- 收稿日期: 2021-01-04
- 修回日期: 2021-09-18
- 刊出日期: 2022-02-01

Research on the Influence of ⁵⁶Fe Evaluation Cross Section of CENDL-3.2 and ENDF/B-Ⅷ.0 on Shielding Calculation

Zhang Bin^1
,,
Ma Xubo^{1
, ,},
Hu Kui¹,
Chen Yixue¹,
Wu Haicheng²

1.
School of Nuclear Science and Engineering, North China Electric Power University, Beijing, 102206, China
2.
China Nuclear Data Center, China Institute of Atomic Energy, Beijing, 102413, China

摘要

摘要: CENDL-3.2评价库对⁵⁶Fe非弹性散射截面进行了更新，为了验证其与ENDF/B-Ⅷ.0评价库中截面以及屏蔽计算能力的差异，通过NJOY2016程序对⁵⁶Fe共振重造后的非弹性散射、总截面等微观截面进行了比较；并制作了多群截面，在⁵⁶Fe非弹性散射能量范围对以⁵⁶Fe为主要核素的3个系列屏蔽基准题ILL-Fe、OKTAVIAN-Fe、IPPE-Fe进行了屏蔽计算性能的比较。结果表明，CENDL-3.2评价库的非弹性散射截面在4~12 MeV能量范围内低于ENDF/B-Ⅷ.0评价库的结果；多群截面基准题验证表明，CENDL-3.2评价库计算结果与实验值总体符合较好；对于OKTAVIAN-Fe基准题，在0.1~1 MeV能量范围内两评价库计算结果吻合较好。此外，所有基准题验证结果都有共同的现象，即在⁵⁶Fe非弹性散射截面占主要贡献的1~10 MeV能量范围内，CENDL-3.2的计算结果比ENDF/B-Ⅷ.0的计算结果偏高。
- ⁵⁶Fe /
- 非弹性散射截面 /
- CENDL-3.2评价库 /
- ENDF/B-Ⅷ.0评价库 /
- 屏蔽计算
Abstract: CENDL-3.2 Library updated the ⁵⁶Fe inelastic scattering cross section. In order to verify the difference of cross-section and the shielding computing ability between the CENDL-3.2 Library and ENDF/B-Ⅷ.0 Library, NJOY2016 program was used to compare the microscopic cross section of ⁵⁶Fe after resonance reconstruction, such as inelastic scattering, total cross section, and the multi-group cross section library was also made. Three series of shielding benchmarks, ILL-Fe, OKTAVIAN-Fe and IPPE-Fe, are selected in the range of ⁵⁶Fe inelastic scattering energy, and ⁵⁶Fe is used as the main nuclide. The results show that the inelastic cross section of CENDL-3.2 Library is lower than that of ENDF/B-Ⅷ.0 Library in the range of 4MeV~12MeV. The multi-group cross-section benchmark verification showed that the calculated results of CENDL-3.2 Library are in good agreement with the experimental values. For OKTAVIAN-Fe benchmark, the results of the two Libraries agree well in the range of 0.1MeV~1MeV. In addition, the same phenomenon is found in all the benchmark tests, that is, in the energy range of 1MeV~10MeV, where the ⁵⁶Fe inelastic cross section is the main contribution, the results of CENDL-3.2 Library are higher than those of ENDF/B-Ⅷ.0 Library.
- ⁵⁶Fe /
- Inelastic scattering cross section /
- CENDL-3.2 /
- ENDF/B-Ⅷ.0 /
- Shielding calculation

HTML全文

图 1 CENDL-3.2库与ENDF/B-Ⅶ.1库、ENDF/B-Ⅷ.0库⁵⁶Fe微观截面结果对比

1 b=10⁻²⁴cm²

Figure 1. Comparison of the Results of ⁵⁶Fe Micro Cross-section between CENDL-3.2, ENDF/B-Ⅶ.1 and ENDF/B-Ⅷ.0 Libraries

下载: 全尺寸图片幻灯片

图 2 MATXS格式多群截面数据库制作及验证流程

Figure 2. The Process of MATXS Format Multi-group Cross-section Library Production and Verification

下载: 全尺寸图片幻灯片

图 3 OKTAVIAN-Fe基准计算值与实验值对比图

Figure 3. Comparison of the Calculated and Experimental Values of OKTAVIAN-Fe Benchmark

下载: 全尺寸图片幻灯片

图 4 ILL-Fe基准题计算值与实验值对比图

Figure 4. Comparison of the Calculated and Experimental Values of ILL-Fe Benchmark

下载: 全尺寸图片幻灯片

图 5 IPPE-Fe基准题模型几何结构图

Figure 5. Geometric Structure of IPPE-Fe Benchmark Model

下载: 全尺寸图片幻灯片

图 6 IPPE-Fe基准计算值与实验值对比图

Figure 6. Comparison of the Calculated and Experimental Values of IPPE-Fe Benchmark

下载: 全尺寸图片幻灯片

图 7 IPPE-Fe基准题3的CENDL-3.2计算结果与ENDF/B-Ⅷ.0计算结果比值

Figure 7. Ratio of Results of CENDL-3.2 to ENDF/B-Ⅷ.0 for the IPPE-Fe Benchmark 3

下载: 全尺寸图片幻灯片

表 1 OKTAVIAN-Fe屏蔽装置材料组成

Table 1. Material Composition of OKTAVIAN-Fe Shielding Device

元素	核子密度/(b⁻¹·cm⁻¹)
Fe	8.3579×10⁻²
Mn	7.6620×10⁻⁴
Si	3.8732×10⁻⁴
C	6.3004×10⁻⁴
P	3.0540×10⁻⁵
S	1.4749×10⁻⁵

下载: 导出CSV

表 2 ILL-Fe基准模型物理参数描述

Table 2. Description of Physical Parameters of ILL-Fe Benchmark Model

参数名	参数值
球壳外半径/cm	38.1
球壳内半径/cm	7.65
密度 /(g·cm⁻³)	7.87
核子密度/ (b⁻¹·cm⁻¹)	0.0849

下载: 导出CSV

表 3 IPPE-Fe基准题几何参数和核子密度

Table 3. Geometric Parameters and Nucleon Density of IPPE-Fe Benchmark

基准题	球壳几何参数			中子平均自由程/m	核子密度/(b⁻¹·cm⁻¹)	径向孔参数r_i (l_i)/ cm	(V’/V)平均值/%
基准题	R/cm	r/cm	壁厚/cm	中子平均自由程/m	核子密度/(b⁻¹·cm⁻¹)	径向孔参数r_i (l_i)/ cm	(V’/V)平均值/%
1	4.5	2.0	2.5	0.5	840	2.0(2.5)	10.6
2	12.0	4.5	7.5	1.6	820	3.2(4), 3.0(3.5)	3.3
3	20.0	1.9	18.1	3.9	830	2.5(10.3), 1.9(7.8)	0.9
4	30.0	2.0	28.0	6.1	830	4(7), 2.5(7.8), 2.0(13.2)	0.6

下载: 导出CSV

参考文献(16)

[1]	LEE C, YANG W S. MC²-3: multigroup cross section generation code for fast reactor analysis[J]. Nuclear Science and Engineering, 2017, 187(3): 268-290. doi: 10.1080/00295639.2017.1320893
[2]	WENNER M T, HAGHIGHAT A, ADAMS J M, et al. Novel investigation of iron cross sections via spherical shell transmission measurements and particle transport calculations for material embrittlement studies[J]. Nuclear Science and Engineering, 2017, 170(3): 207-233.
[3]	CHADWICK M B, DUPONT E, BAUGE E, et al. The CIELO collaboration: neutron reactions on ¹H, ¹⁶O, ⁵⁶Fe, ^{235, 238}U, and ²³⁹Pu[J]. Nuclear Data Sheets, 2014, 118: 1-25. doi: 10.1016/j.nds.2014.04.002
[4]	钱晶,葛智刚,刘廷进,等. 20MeV以下快中子与⁵⁶Fe非弹性散射截面的分歧研究[J]. 原子核物理评论,2017, 34(3): 514-519. doi: 10.11804/NuclPhysRev.34.03.514
[5]	GE Z G, XU R R, WU H C, et al. CENDL-3.2: The new version of Chinese general purpose evaluated nuclear data library[J]. EPJ Web of Conferences, 2020, 239: 09001. doi: 10.1051/epjconf/202023909001
[6]	CHADWICK M B, HERMAN M, OBLOŽINSKÝ P, et al. ENDF/B-VII. 1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data[J]. Nuclear Data Sheets, 2011, 112(12): 2887-2996. doi: 10.1016/j.nds.2011.11.002
[7]	BROWN D A, CHADWICK M B, CAPOTE R, et al. ENDF/B-VIII. 0: The 8^th major release of the nuclear reaction data library with cielo-project cross sections, new standards and thermal scattering data[J]. Nuclear Data Sheets, 2018, 148: 1-142. doi: 10.1016/j.nds.2018.02.001
[8]	MACFARLANE R, MUIR D W, BOICOURT R M, et al. The NJOY nuclear data processing system, version 2016: LA-UR-17-20093[R]. Los Alamos, United States: Los Alamos National Laboratory, 2017.
[9]	MACFARLANE R E. TRANSX 2: a code for interfacing MATXS cross-section libraries to nuclear transport codes: LA-12312-MS[R]. NM, United States: Los Alamos National Laboratory, 1992
[10]	ENGLE JR W W. A users manual for ANISN: a one dimensional discrete ordinates transport code with anisotropic scattering: K-1693 [R]. United States: Oak Ridge Gaseous Diffusion Plant, 1967
[11]	SUMITA K, TAKAHASHI A, HASHIKURA H, et al. Measurements of neutron leakage spectra from 50.32 cm radius iron sphere: A-83-07[R]. Japan: Osaka University, 1983.
[12]	HASHIKURA H, HAIKAWA K, TAKAHASHI A, et al. Neutron leakage spectra from a large iron sphere pulsed with 14 MeV neutrons[C]//Proceedings of the NEA Specialists' Meeting on Shielding Benchmarks, Saclay, France, 1984
[13]	JOHNSON R H. Integral tests of neutron cross sections for iron, nobium, beryllium, and polyethylene[D]. Urbana, Illinois: University of Illinois at Urbana-Champaign, 1975.
[14]	WILLIAMS M L, ABOUGHANTOUS C, ASGARI M, et al. Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V and ENDF/B-VI iron evaluations[J]. Annals of Nuclear Energy, 1991, 18(10): 549-565. doi: 10.1016/0306-4549(91)90055-3
[15]	DEVKIN B V, KOBOZEV M G, SIMAKOV S P, et al. Neutron leakage spectra from iron spheres[C]//Proceedings of the 18th Symposium on Fusion Technology, 22-26 Aug 1994, Karlsruhe, 1994
[16]	NUNNENMANN E, FISCHER U. V&V analyses of the GEANT4 Monte Carlo code toolkit with computational and experimental fusion neutronics benchmarks[J]. Fusion Engineering and Design, 2019, 146: 1579-1582. doi: 10.1016/j.fusengdes.2019.02.132