Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E 706 (IID)
|Publication Date:||27 October 1989|
|ICS Code (Nuclear power plants. Safety):||27.120.20|
1.1 Need for Neutronics Calculations--An accurate calculation of the neutron fluence and fluence rate at several locations is essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in the pressure vessel. Exposure parameter values may be obtained directly from calculations or indirectly from calculations that are adjusted with dosimetry measurements; Guide E 944 and Practice E 853 define appropriate computational procedures.
1.3 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.