TY - GEN
T1 - Safety margin characterization for atr high power fueled experiments
AU - Dave, Akshay
AU - Wang, Yu Jou
AU - Hu, Lin Wen
AU - Sun, Kaichao
AU - Nielsen, Joseph
AU - Murray, Paul
AU - Marlow, Ryan
N1 - Publisher Copyright:
© 2018 American Nuclear Society. All rights reserved.
PY - 2018
Y1 - 2018
N2 - The current safety basis (SAR-153) for the Advanced Test Reactor (ATR) ensures that the plant protection criteria is maintained for all Condition 2 events by verifying that, for a Condition 2 Flow Coastdown Transient and Condition 2 Reactivity Insertion Accident, the Departure from Nucleate Boiling (DNB) Ratio (DNBR) is greater than two. The basis used to establish this limit is not well defined but may be traced to research reactor licensing based on overly conservative thermal hydraulic criteria. This limitation may not be applicable to reactor experiments because the quantity of fissionable material and fission product inventory in experiments is much less than that of the reactor core, and may prevent or limit future experimental testing in the ATR. In particular, fueled experiments may be excluded from irradiation in ATR if the desired fission power cannot be achieved due to these safety criteria. This study will evaluate the DNBR using various CHF correlations and consider the impacts of changing the limit to a more suitable thermal hydraulic safety limit for fueled experiments, such as Onset of Nucleate Boiling (ONB), Onset of Significant Voiding (OSV), and Onset of Flow Instability (OFI). The study utilizes a BEPU (bestestimate plus uncertainty) statistical approach that maintains 3σ from thermal hydraulic safety limit during Condition 2 transients. Modeling parameters of different correlations will be evaluated by considering the associated uncertainties. The study will eventually provide recommendations to support any safety basis changes that can expand the experimental operating envelope of the ATR without a compromise in safety. The preliminary results indicate that large safety margins can be kept for Critical Heat Flux (CHF) based DNB at almost all conditions. DNBR only reaches slightly below two when using Groeneveld's CHF Look-up Table (LUT) at peak transient condition with all conservative power multipliers applied. At all studied conditions, OFI ratios are found always greater than two and significant margins have been kept from OSV. ONB only occurs at steady-state when all conservative power multipliers are applied. Preliminary results involving an additional method with Dakota/RAVEN coupled to RELAP5 is presented.
AB - The current safety basis (SAR-153) for the Advanced Test Reactor (ATR) ensures that the plant protection criteria is maintained for all Condition 2 events by verifying that, for a Condition 2 Flow Coastdown Transient and Condition 2 Reactivity Insertion Accident, the Departure from Nucleate Boiling (DNB) Ratio (DNBR) is greater than two. The basis used to establish this limit is not well defined but may be traced to research reactor licensing based on overly conservative thermal hydraulic criteria. This limitation may not be applicable to reactor experiments because the quantity of fissionable material and fission product inventory in experiments is much less than that of the reactor core, and may prevent or limit future experimental testing in the ATR. In particular, fueled experiments may be excluded from irradiation in ATR if the desired fission power cannot be achieved due to these safety criteria. This study will evaluate the DNBR using various CHF correlations and consider the impacts of changing the limit to a more suitable thermal hydraulic safety limit for fueled experiments, such as Onset of Nucleate Boiling (ONB), Onset of Significant Voiding (OSV), and Onset of Flow Instability (OFI). The study utilizes a BEPU (bestestimate plus uncertainty) statistical approach that maintains 3σ from thermal hydraulic safety limit during Condition 2 transients. Modeling parameters of different correlations will be evaluated by considering the associated uncertainties. The study will eventually provide recommendations to support any safety basis changes that can expand the experimental operating envelope of the ATR without a compromise in safety. The preliminary results indicate that large safety margins can be kept for Critical Heat Flux (CHF) based DNB at almost all conditions. DNBR only reaches slightly below two when using Groeneveld's CHF Look-up Table (LUT) at peak transient condition with all conservative power multipliers applied. At all studied conditions, OFI ratios are found always greater than two and significant margins have been kept from OSV. ONB only occurs at steady-state when all conservative power multipliers are applied. Preliminary results involving an additional method with Dakota/RAVEN coupled to RELAP5 is presented.
UR - http://www.scopus.com/inward/record.url?scp=85050114466&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:85050114466
T3 - Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
SP - 156
EP - 164
BT - Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
PB - American Nuclear Society
T2 - 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
Y2 - 8 April 2018 through 11 April 2018
ER -