首页> 外文会议>International conference on the physics of reactors;PHYSOR 2012 >SIMPLIFIED TREATMENT OF EXACT RESONANCE ELASTIC SCATTERING MODEL IN DETERMINISTIC SLOWING DOWN EQUATION
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SIMPLIFIED TREATMENT OF EXACT RESONANCE ELASTIC SCATTERING MODEL IN DETERMINISTIC SLOWING DOWN EQUATION

机译:确定性减慢方程的精确共振弹性散射模型的简化处理

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Simplified treatment of resonance elastic scattering model considering thermal motion of heavy nuclides and the energy dependence of the resonance cross section was implemented into NJOY [1]. In order to solve deterministic slowing down equation considering the effect of up-scattering without iterative calculations, scattering kernel for heavy nuclides is pre-calculated by the formula derived by Ouisloumen and Sanchez [2], and neutron spectrum in up-scattering term is expressed by NR approximation. To check the verification of the simplified treatment, the treatment is applied to U-238 for the energy range from 4eV to 200eV. Calculated multi-group capture cross section of U-238 is greater than that of conventional method and the increase of the capture cross sections is remarkable as the temperature becomes high. Therefore Doppler coefficient calculated in UO_2 fuel pin is calculated more negative value than that on conventional method. The impact on Doppler coefficient is equivalent to the results of exact treatment of resonance elastic scattering reported in previous studies [2-7].The agreement supports the validation of the simplified treatment and therefore this treatment is applied for other heavy nuclide to evaluate the Doppler coefficient in MOX fuel. The result shows that the impact of considering thermal agitation in resonance scattering in Doppler coefficient comes mainly from U-238 and that of other heavy nuclides such as Pu239, 240 etc. is not comparable in MOX fuel.
机译:考虑到重核素的热运动和共振截面的能量依赖性,共振弹性散射模型的简化处理被实现为NJOY [1]。为了在不进行迭代计算的情况下考虑向上散射的影响来解决确定性减慢方程,通过Ouisloumen和Sanchez [2]推导的公式预先计算了重核素的散射核,并表示了向上散射项的中子谱通过NR近似。为了检查简化处理的验证,对U-238进行了从4eV到200eV能量范围的处理。 U-238的计算的多组俘获截面大于常规方法,并且随着温度升高,俘获截面的增加是显着的。因此,与传统方法相比,在UO_2燃料销中计算出的多普勒系数的负值更大。对多普勒系数的影响等同于先前研究中报道的对共振弹性散射的精确治疗结果[2-7]。该协议支持简化治疗的验证,因此该治疗可用于其他重核素以评估多普勒MOX燃料中的系数。结果表明,在多普勒系数共振散射中考虑热搅动的影响主要来自U-238,而其他重核素如Pu239、240等对MOX燃料的影响不大。

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