Validation of capture reactions cross sections in 252Cf(s.f.) neutron field

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes Pub Date : 2024-11-10 DOI:10.1016/j.apradiso.2024.111586

Martin Schulc , Evžen Novák , Jan Šimon , Alena Krechlerová , Michal Košťál , Roberto Capote

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引用次数: 0

Abstract

We have investigated following capture reactions: ¹⁹⁷Au(n,g)¹⁹⁸Au, ⁶³Cu(n,g)⁶⁴Cu, ⁴⁵Sc(n,g)⁴⁶Sc, ¹⁸¹Ta(n,g)¹⁸²Ta, ¹⁴⁰Ce(n,g)¹⁴¹Ce, ¹³⁹La(n,g)¹⁴⁰La, ¹⁷⁶Yb(n,g)¹⁷⁷Yb, ⁵⁵Mn(n,g)⁵⁶Mn, and ¹⁴¹Pr(n,g)¹⁴²Pr in a standard ²⁵²Cf(s.f.) neutron field. The experimentally derived reaction rates were compared with calculations using state-of-the-art libraries IRDFF-II, ENDF/B-VIII.0, JENDL-5 and JEFF-3.3 performed in MCNP6.2 transport code. The experiment was focused on capture reactions in high energy neutron range. To suppress scattered low energy neutrons, all activation materials were enclosed by a spherical cadmium surface of 30 cm in diameter. Experimentally derived reaction rates of ¹⁹⁷Au(n,g)¹⁹⁸Au, ⁶³Cu(n,g)⁶⁴Cu reactions agree with calculations using all state-of-the-art nuclear data libraries. The highest discrepancies were found when evaluating ¹³⁹La(n,g)¹⁴⁰La and ⁵⁵Mn(n,g)⁵⁶Mn reactions utilizing all libraries. Experimental reaction rates applying data from the JENDL-5 library agree very well with the results of other reactions except for the ⁴⁵Sc(n,g)⁴⁶Sc reaction. ¹⁸¹Ta(n,g)¹⁸²Ta reaction rate does not agree within uncertainties using any library. The ¹⁷⁶Yb(n,g)¹⁷⁷Yb reaction rate agrees reasonably well only when performing calculation using JENDL-5 and ENDF/B-VIII.0 libraries, unlike JEFF-3.3 library. ¹⁴⁰Ce(n,g)¹⁴¹Ce and ¹⁴¹Pr(n,g)¹⁴²Pr reaction rates applying JEFF-3.3 and ENDF/B-VIII.0 libraries do not agree within uncertainties.

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验证 252Cf(s.f.) 中子场中的俘获反应截面。

我们对以下俘获反应进行了研究：197Au(n,g)198Au、63Cu(n,g)64Cu、45Sc(n,g)46Sc、181Ta(n,g)182Ta、140Ce(n,g)141Ce、139La(n,g)140La、176Yb(n,g)177Yb、55Mn(n,g)56Mn 和 141Pr(n,g)142Pr。实验得出的反应速率与在 MCNP6.2 传输代码中使用最先进库 IRDFF-II、ENDF/B-VIII.0、JENDL-5 和 JEFF-3.3 进行的计算结果进行了比较。实验的重点是高能中子范围内的俘获反应。为了抑制散射的低能中子，所有活化材料都被一个直径为 30 厘米的球形镉表面所包围。实验得出的 197Au(n,g)198Au、63Cu(n,g)64Cu 反应速率与使用所有最先进的核数据库进行的计算结果一致。在评估 139La(n,g)140La和 55Mn(n,g)56Mn反应时，发现所有库的数据差异最大。除了 45Sc(n,g)46Sc反应之外，应用 JENDL-5 库数据的实验反应速率与其他反应的结果非常吻合。181Ta(n,g)182Ta反应速率与使用任何资料库得出的结果在不确定范围内都不一致。176Yb(n,g)177Yb 反应速率只有在使用 JENDL-5 和 ENDF/B-VIII.0 库进行计算时才会比较一致，而不像 JEFF-3.3 库。使用 JEFF-3.3 和 ENDF/B-VIII.0 库计算的 140Ce(n,g)141Ce 和 141Pr(n,g)142Pr 反应速率在不确定范围内不一致。

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来源期刊

Applied Radiation and Isotopes 工程技术-核科学技术

CiteScore

3.00

自引率

12.50%

发文量

406

审稿时长

13.5 months

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