首页> 外文会议>Waste management 2004 symposium (WM'04): waste management, energy security and a clean environment >Probabilistic Versus Deterministic Analysis for Demonstration of Compliance with the Dose Criteria in 10 CFR Part 20,Subpart E
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Probabilistic Versus Deterministic Analysis for Demonstration of Compliance with the Dose Criteria in 10 CFR Part 20,Subpart E

机译:证明与10 CFR Part 20中E部分剂量标准符合性的概率对确定性分析

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The U.S.Nuclear Regulatory Commission(NRC)promulgated its regulations on the“Radiological Criteria for License Termination”in 10 CFR Part 20,Subpart E.The regulations require that,for the release of sites for unrestricted use,the total effective dose equivalent(TEDE)to an average member of a critical group, resulting from residual radioactivity that is distinguishable from background radiation,does not exceed 0.25 milliSievert per year(mSv/yr),(25 millirem/yr(mrem/yr)).Subpart E also requires that the residual radioactivity has been reduced to levels that are as low as is reasonably achievable(ALARA).In addition, Subpart E establishes the criteria for license termination with restrictions on future land use,as long as specific conditions are met.Finally,subpart E provides alternate criteria for license termination in unusual situations where the site may exceed the 0.25 mSv/yr(25 mrem/yr)limit,but would not be permitted to exceed 1.0 mSv/yr(100 mrem/yr)or 5.0 mSv/yr(500 mrem/yr),under certain conditions. rnLicensees,staff,and/or stakeholders may demonstrate compliance with the dose criteria through site-specific dose impact analysis to establish derived concentration guideline levels(DCGLs).Site-specific dose impacts analysis may also be conducted to assess remedial actions or options for site release restrictions based on measured concentrations of residual radioactivity at the site. rnThe NRC is committed to a risk-informed performance based(RIPB)approach in regulatory decision-making and licensing activities.Staff commonly uses probabilistic analysis to assess the significance of risk and uncertainties in dose analyses.The analyst typically considers realistic bounding conditions based on probabilistic distributions of input parameters and evaluate uncertainties in the dose outputs.Licensees and stakeholders currently use two approaches for dose analysis.One approach is based on a deterministic methodology,which typically employs a highly“conservative”single value for each parameter assumed to bound variability and uncertainty in site specific conditions.The second approach is based on a probabilistic methodology which employs sensitivity and uncertainty analysis of input parameters using probabilistic distributions of sensitive parameters. rnNRC staff have conducted dose analyses for decommissioning sites using both deterministic and probabilistic approaches to review and evaluate licensees’derived concentration guideline levels(DCGLs)equivalent to the dose criteria in 10 CFR Part 20,Subpart E.Review of licensee’s dose analysis includes assessment of input parameters and evaluation of the dose outputs for the two approaches.Based on staff analyses,and using common codes/models acceptable by most Federal agencies,the deterministic analysis approach can produce unrealistically conservative dose values.Probabilistic dose analyses,however,generally produce more realistic dose results and help define the associated uncertainties.Detailed comparative analyses of the two approaches with an actual example is presented.
机译:美国核监管委员会(NRC)在10 CFR第20部分E子部分中颁布了有关“许可证终止的放射学标准”的法规。该法规要求,为了释放不受限制的使用场所,总有效剂量当量(TEDE) )至临界组的一个普通成员,这是由与本底辐射有区别的残留放射性引起的,每年不超过0.25毫希沃特(mSv / yr),(25毫瑞姆/yr(mrem/yr)).E分部还要求剩余的放射性已降低到合理可达到的低水平(ALARA)。此外,子部分E确立了终止许可的标准,并在满足特定条件的情况下限制了未来的土地使用。最后,子部分E为在站点可能超过0.25 mSv / yr(25 mrem / yr)限制但不允许超过1.0 mSv / yr(100 mrem / yr)或5.0 mSv / yr的异常情况下提供终止许可证的替代标准(500 mrem / yr),以下一定条件下。 rn执照持有人,员工和/或利益相关者可以通过针对具体地点的剂量影响分析证明其符合剂量标准,以建立派生的浓度指导水平(DCGL)。还可以进行针对具体地点的剂量影响分析以评估补救措施或针对地点的选择根据现场残留放射性的测量浓度限制释放。 NRC致力于在监管决策和许可活动中采用基于风险知情的绩效(RIPB)方法.Staff通常使用概率分析来评估剂量分析中风险和不确定性的重要性。分析人员通常根据输入参数的概率分布并评估剂量输出中的不确定性。被许可方和涉众目前使用两种方法进行剂量分析。一种方法基于确定性方法,对于确定为可变性的每个参数,通常使用高度“保守”的单个值第二种方法基于一种概率论方法,该方法采用敏感性参数的概率分布对输入参数进行敏感性和不确定性分析。 NRC工作人员使用确定性和概率方法对退役场所进行剂量分析,以审查和评估与10 CFR第20部分E子部分中的剂量标准等效的许可方衍生浓度准则水平(DCGL)。对许可方剂量分析的评估包括对两种方法的输入参数和剂量输出评估。基于人员分析,并使用大多数联邦机构可接受的通用代码/模型,确定性分析方法可能会产生不切实际的保守剂量值。然而,概率性剂量分析通常会产生更多实际的剂量结果并帮助定义相关的不确定性。给出了两种方法的详细比较分析,并带有一个实际的例子。

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