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The Fast Neutron Fluence and the Activation Detector Activity Calculations Using the Effective Source Method and the Adjoint Function

机译：利用有效源方法和伴随函数计算快速中子通量和活化检测器的活度

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This paper describes the application of effective source in forward calculations and the adjoint method to the solution of fast neutron fluence and activation detector activities in the reactor pressure vessel (RPV) and RPV cavity of a VVER-440 reactor. Its objective is the demonstration of both methods on a practical task. The effective source method applies the Boltzmann transport operator to time integrated source data in order to obtain neutron fluence and detector activities. By weighting the source data by time dependent decay of the detector activity, the result of the calculation is the detector activity. Alternatively, if the weighting is uniform with respect to time, the result is the fluence. The approach works because of the inherent linearity of radiation transport in non-multiplying time-invariant media. Integrated in this way, the source data are referred to as the effective source. The effective source in the forward calculations method thereby enables the analyst to replace numerous intensive transport calculations with a single transport calculation in which the time dependence and magnitude of the source are correctly represented. In this work, the effective source method has been expanded slightly in the following way: neutron source data were performed with fewgroup method calculation using the active core calculation code MOBY-DICK. The follow-up neutron transport calculation was performed using the neutron transport code TORT to perform multigroup calculations. For comparison, an alternative method of calculation has been used based upon adjoint functions of the Boltzmann transport equation. Calculation of the three-dimensional (3-D) adjoint function for each required computational outcome has been obtained using the deterministic code TORT and the cross section library BGL440. Adjoint functions appropriate to the required fast neutron flux density and neutron reaction rates have been calculated for several significant points within the RPV and RPV cavity of the VVER-440 reactor. Both of calculation methods are briefly described and the results are compared.
机译：本文介绍了有效源在正演计算中的应用以及伴随方法在解决VVER-440反应堆压力容器（RPV）和RPV腔中快速中子注量和活化检测器活动方面的问题。其目的是在实际任务中演示这两种方法。有效的源方法将玻尔兹曼输运算子应用于集成源数据的时间，以获得中子注量和探测器活动。通过根据探测器活动的时间依赖性衰减对源数据进行加权，计算结果就是探测器活动。或者，如果权重相对于时间是均匀的，则结果是注量。该方法之所以有效，是因为辐射在非乘性时不变介质中的固有传输线性。通过这种方式进行集成，将源数据称为有效源。因此，前向计算方法中的有效源使分析人员可以用单个输运计算代替大量密集输运计算，在该计算中，可以正确表示源的时间依赖性和强度。在这项工作中，有效源方法已通过以下方式略有扩展：使用有源堆芯计算代码MOBY-DICK以少几组方法计算来执行中子源数据。后续的中子输运计算使用中子输运代码TORT进行，以进行多组计算。为了比较，已经使用了基于玻耳兹曼输运方程的伴随函数的另一种计算方法。已使用确定性代码TORT和横截面库BGL440获得了每个所需计算结果的三维（3-D）伴随函数的计算。已经针对VVER-440反应堆RPV和RPV腔内的几个重要点计算了适合于所需快速中子通量密度和中子反应速率的伴随函数。简要介绍了这两种计算方法并比较了结果。

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