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Category:Report
MONTHYEARML22173A2032022-06-21021 June 2022 University of California - Davis, Response to NRC Request for Additional Information Letter Dated June 3rd 2022 Regarding License Renew Al Application - Appendix B, Radiological Impact of Accidents ML21265A5532021-09-24024 September 2021 Nniv. of California - Davis: Uncontrolled Withdrawal of a Control Rod Nonlinear Worth ML21265A5472021-09-23023 September 2021 Criticality Safety Analysis for MNRC Spent Fuel Pits ML21265A5512021-09-22022 September 2021 Maximum Reactivity Insertion ML21265A5502021-09-22022 September 2021 Calculation of Negative Void Coefficient of MNRC Core ML21265A5492021-09-22022 September 2021 MNRC Soil Permeability Information ML21265A5462021-09-22022 September 2021 Negative Temperature Co-Efficient ML21265A5432021-09-22022 September 2021 Univ. of California - Davis: Analysis for Blockage of Fuel Channel Potential ML21265A5452021-09-22022 September 2021 Appendix B: Radiologcal Impact of Accidents ML21265A5442021-06-24024 June 2021 Univ. of California - Davis: Analysis of Fuel Temperature After LOCA 20210624 ML20261H3882020-09-17017 September 2020 Updated UC Davis MNRC Reactor Proposed License Renewal Ipac Trust Resources Report ML18179A5062018-06-0606 June 2018 Mcclellan Nuclear Research Center Financial Qualification Report University of California Davis ML18179A5091999-10-31031 October 1999 University of California - Davis/Mcclellan Nuclear Radiation Center Selection and Training Plan for Reactor Personnel 2022-06-21
[Table view] Category:Technical
MONTHYEARML22173A2032022-06-21021 June 2022 University of California - Davis, Response to NRC Request for Additional Information Letter Dated June 3rd 2022 Regarding License Renew Al Application - Appendix B, Radiological Impact of Accidents ML21265A5532021-09-24024 September 2021 Nniv. of California - Davis: Uncontrolled Withdrawal of a Control Rod Nonlinear Worth ML21265A5472021-09-23023 September 2021 Criticality Safety Analysis for MNRC Spent Fuel Pits ML21265A5512021-09-22022 September 2021 Maximum Reactivity Insertion ML21265A5502021-09-22022 September 2021 Calculation of Negative Void Coefficient of MNRC Core ML21265A5492021-09-22022 September 2021 MNRC Soil Permeability Information ML21265A5462021-09-22022 September 2021 Negative Temperature Co-Efficient ML21265A5432021-09-22022 September 2021 Univ. of California - Davis: Analysis for Blockage of Fuel Channel Potential ML21265A5452021-09-22022 September 2021 Appendix B: Radiologcal Impact of Accidents ML21265A5442021-06-24024 June 2021 Univ. of California - Davis: Analysis of Fuel Temperature After LOCA 20210624 ML20261H3882020-09-17017 September 2020 Updated UC Davis MNRC Reactor Proposed License Renewal Ipac Trust Resources Report ML18179A5062018-06-0606 June 2018 Mcclellan Nuclear Research Center Financial Qualification Report University of California Davis ML18179A5091999-10-31031 October 1999 University of California - Davis/Mcclellan Nuclear Radiation Center Selection and Training Plan for Reactor Personnel 2022-06-21
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The analysis below is intended to satisfy question 4-6 of the draft RAIs. Ultimately this analysis needs to be added to chapter 4.5 of the SAR. The calculation below was performed using MCNP version 5.
Calculation of Negative Void Coefficient of MNRC Core The reactivity worth of a complete loss of all water inside and surround the core was calculated based on the OCC configuration with burnup levels as of 9/1/20, where excess reactivity was ~$4.50 (ambient temperatures and no xenon). Without any water inside or surrounding the reactor the reactor was found to be subcritical by $21.88 with all control rods fully withdrawn. Even if core excess was $9.25 instead of $4.50 the reactor would still remain subcritical by over $15.00 with no water and all control rods fully withdrawn. This results in a reactor negative void coefficient of approximately $0.25/1%
water removed from the core. Note this is an approximate value because it is averaged throughout the core, meaning voids in different locations in the core will have different values. This gives strong evidence that during an actual LOCA event, the core will become subcritical (even with all controls rods fully withdrawn) when the reactor tank water falls to approximately half way down the active region of the fuel. This results are in general agreement with other TRIGA reactors.