Resolution of Generic Safety Issues: NMSS-0007. Criticality Benchmarks Greater than 5% Enrichment (Rev. 2) ( NUREG-0933, Main Report with Supplements 1–35 )

DESCRIPTION

The importance of computer software (methods and data) in establishing the criticality safety of systems with fissile material is increasing as licensees work to optimize facilities and storage/transport packages at the same time that access to experimental data is decreasing. Available experimental data are insufficient to validate nuclear criticality safety evaluations for all required configurations at U²³⁵ enrichments in the range of 5% to 20%. This issue was identified¹⁷⁰⁹ by NMSS to develop and confirm the adequacy of methods, analytical tools, and guidance for criticality safety software to be used in licensing nuclear facilities.

BACKGROUND

Computer codes used for criticality calculations must be benchmarked against critical experiments that represent the specific fissile materials, configurations, moderation, and neutron-poisoning conditions that represent the facility being licensed. However, it is well recognized that existing critical benchmark experiments will never precisely match these conditions. In addition, there are fewer benchmark experiments that are available at higher enrichment ranges [e.g., between 5 to 20 percent and lower-moderation (i.e., H/X, where H is hydrogen and X is fissile media)] ranges, that could be of future interest to potential applicants. Methods are needed to extend the range of applicability of current benchmark experiments via sensitivity/uncertainty (S/U) analysis techniques.

NMSS has performed extensive work with Oak Ridge National Laboratory (ORNL) to further develop criticality safety computer codes [e.g., Standardized Computer Analyses for Licensing Evaluation (SCALE)] to address these challenges. The final reports for the S/U methods were published in November 1999 as Volumes I ¹⁹²³ and 2¹⁹²⁴ of NUREG/CR-6655. The reports covered the following subjects: (1) methodology for defining range of applicability, including extensions of enrichments from 5 to 11 percent; (2) test applications and results of the method; (3) test application for higher enrichments using foreign experiments; and (4) feasibility study for extending the method to multidimensional analyses, such as transport casks and reactor fuel.

DISCUSSION

Results of the test applications of the ORNL methods showed that, for simple geometries with neutron spectra that are well-moderated (high H/X), benchmark experiments at 5 percent enrichment are applicable to calculations up to 11 percent enrichment. On the other hand, these test applications also show that benchmark experiments at intermediate and higher H/X values are not applicable to calculations at very low H/X. There are relatively few benchmarks at these very low H/X values for many compositions of interest to low-enriched uranium licensees.

Although licensees must apply the ORNL method to each individual process, to determine an acceptable subcritical margin, the results indicated that there may be situations where there are no applicable benchmarks. In these cases, the method provides sensitivity and uncertainty information, to help designers allow adequately large margins to cover the lack of benchmark validation. The computer codes [(i.e., Tools for Sensitivity and Uncertainty Analysis Methodology Implementation (TSUNAMI)] for S/U methods were incorporated into the release of SCALE 5.0 in 2004. The TSUNAMI code in SCALE 5.0 systematically quantifies the degree of similarity between a set of critical experiments and applications. For those applications where few benchmarks exist, as described previously for low H/X values, the TSUNAMI code can be used to apply adequately large margins to ensure the application is properly validated by SCALE 5.0.

In June 2006, staff issued Fuel Cycle Safety and Safeguards (FCSS) Interim Staff Guidance (ISG) -10 ¹⁹²⁵, "Justification of Minimum Margin of Subcriticality for Safety". The ISG clarified guidance to the NRC staff when reviewing criticality safety analyses in integrated safety analysis, license applications, or amendment requests or other related licensing activities for fuel cycle facilities, under 10 CFR Part 70. The ISG communicates the acceptability of the TSUNAMI computer code in SCALE 5.0, as one method for determining minimum margins of subcriticality with limited benchmark experiments. For applications where few benchmarks exist, TSUNAMI can be used to apply larger margins to ensure validity of the SCALE criticality codes. Further benchmark experiments may be needed if future applicants request lower margins.

CONCLUSION

The issue was initially given a low priority ranking¹⁷⁰⁹ which was later changed to a high priority.¹⁷⁸⁷This issue was closed out ¹⁹²⁶ after the issuance of FCSS ISG-10, as the final milestone required to close out the GI.

REFERENCES

0235. Memorandum for H. Denton from R. DeYoung, "TMI Action Plan Items Still Pending," June 10, 1982. [8401170101] 1709. Memorandum for J. Craig from F. Combs, "Submittal of New Generic Issues for Tracking in the Generic Issues Management and Control System (GIMCS)," June 4, 1998. [9806090180] 1787. Memorandum for F. Eltawila from D. Cool, "NMSS Input for Second Quarter FY-2001 Update of the Generic Issue Management Control System," April 12, 2001. [ML011000117] 1923. NUREG/CR-6655, Vol. 1, "Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation, Methods Development," U.S. Nuclear Regulatory Commission, November 1999. [ML003726900] 1924. NUREG/CR-6655, Vol. 2, "Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation, Illustrative Applications and Initial Guidance," U.S. Nuclear Regulatory Commission, November 1999. [ML003726890] 1925. Fuel Cycle Safety and Safeguards (FCSS) Interim Staff Guidance (ISG)-10, "Justification of Minimum Margin of Subcriticality for Safety," June 15, 2006. [ML061650370] 1926. Memorandum for L. Reyes from M. Weber, "Closure of Generic Issue NMSS-0007, 'Criticality Benchmarks Greater than 5% Enrichment,'" August 28, 2007. [ML072340091]