A phenomena identification and ranking table(PIRT) was developed for a main steam line break (MSLB) event for the Advanced Power Reactor-1400 (APR-1400). The selectee event was a double-ended steam line break at full power, with the reactor coolant pump running. The developmental panel selected th...
A phenomena identification and ranking table(PIRT) was developed for a main steam line break (MSLB) event for the Advanced Power Reactor-1400 (APR-1400). The selectee event was a double-ended steam line break at full power, with the reactor coolant pump running. The developmental panel selected the fuel performance as the primary safety criterion during the ranking process. The plant design data, the results of the APR-1400 safety analysis, and the results of an additional best-estimate analysis by the MARS computer code were used in the development of the PIRT. The period of the transient was composed of three phases: pre-trip, rapid cool-down, and safety injection. Based on the relative importance to the primary evaluation criterion, the ranking of each system, component, and phenomenon/process was performed for each time phase. Finally, the knowledge-level for each important process for certain components was ranked in terms of existing knowledge. The PIRT can be used as a guide for planning cost-effective experimental programs and for code development efforts, especially for the quantification of those processes and/or phenomena that are highly important, but not well understood.
A phenomena identification and ranking table(PIRT) was developed for a main steam line break (MSLB) event for the Advanced Power Reactor-1400 (APR-1400). The selectee event was a double-ended steam line break at full power, with the reactor coolant pump running. The developmental panel selected the fuel performance as the primary safety criterion during the ranking process. The plant design data, the results of the APR-1400 safety analysis, and the results of an additional best-estimate analysis by the MARS computer code were used in the development of the PIRT. The period of the transient was composed of three phases: pre-trip, rapid cool-down, and safety injection. Based on the relative importance to the primary evaluation criterion, the ranking of each system, component, and phenomenon/process was performed for each time phase. Finally, the knowledge-level for each important process for certain components was ranked in terms of existing knowledge. The PIRT can be used as a guide for planning cost-effective experimental programs and for code development efforts, especially for the quantification of those processes and/or phenomena that are highly important, but not well understood.
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문제 정의
The panel agreed that the PIRT process should not be biased on the application for designing the Integral Effect Test (IET). The panel will look at all the important aspects of the MSLB for both the experimental programs and the code development efforts.
the APR-1400. This paper discusses the process of developing a PIRT for a main steam line break (MSLB) event for the APR-1400. A team of experts from research institutes, industries, and the regulatory body contributed to the development of the PIRT.
가설 설정
The second criterion is the limit on the fuel failure, determined by a pre-trip fuel failure and a post-trip fuel failure. The panel decided to focus on fuel performance, as it is directly related to the off-site dose. It is assumed that Architect Engineer (AE) would provide a large enough safety-margin for the containment.
제안 방법
A comparative analysis was performed by the MARS computer code against that provided in the APR 1400 SAR, which was analyzed by the CESEC computer code. Major initial and boundary conditions are provided in Table 1.
Analyses were performed for both a main steam line break at full power with the reactor coolant pump running (SLBFP) and a main steam break at full power with a loss of offsite power (SLBFPLOP). It is a double-ended guillotine break.
In large part, the initial ranking of high-level systems, components, and phenomena are based on the collective knowledge of the expert panel, though the panel may also utilize relevant information from computer code simulations, if available. During the PIRT meeting, further analyses to confirm the ranking assigned were suggested for the following cases: (1) the comparison of the cold leg injection and direct vessel injection case for MSLB at full power with the reactor coolant pumps running, to evaluate the boron transport phenomena; and (2) the evaluation of the effects of the upp은r head structure, by performing a sensitivity study on the heat structure.
It is assumed that Architect Engineer (AE) would provide a large enough safety-margin for the containment. In addition, both the pure thermal hydraulics and the phenomena related to a reactivity feedback should examined.
The PIRT development employed the collective expertise of the panel members, as well as the results of the APR-1400 SSAR analysis, performed by a conservative CESECcomputer code, and the results by the MARS best-estimate analysis computer code. The question put to the panel was "How do the team members discover what they do not know?" with respect to expanding their state-of-the-art knowledge.
It is a double-ended guillotine break. The conservative input data, including the set points and the capacity of the safety systems used in the SSAR analysis, were used in the MARS analysis to make a fair comparison of the thermal hydraulic response of the sy마em.
To maximize the offsite dose [1, 9], the event scenario presented in the APR-1400 SSAR was somewhat distorted. Therefore, a best-estimate analysis was necessary to make a balanced judgment on the fundamental physics. The best estimate analysis was performed by the MARS computer code [10].
데이터처리
The selected event was a main steam line break at full power with a double-ended guillotine break. The major phenomena involved, the results of a conservative analysis in the APR-1400, and a best estimate analysis are provided by the MARS analysis.
이론/모형
Therefore, a best-estimate analysis was necessary to make a balanced judgment on the fundamental physics. The best estimate analysis was performed by the MARS computer code [10].
후속연구
However, the thermal hydraulic condition during the blow down of the steam generator is far from the design condition. Therefore, the heat-transfer in the U-t나be bank, having a complex geometry for the off-design conditions, needs to be investigated further.
참고문헌 (12)
KEPCO, 2001, APR-1400 SSAR, Chapter 15
G. E. Wilson, B. E. Boyack, 1998, The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis, Nucl. Eng. Des. 186, 23-37
G. E. Wilson, C. D. Fletcher, C. B. Davis, J. D. Burtt, T. J. Boucher, 1997, Phenomena Identification and Ranking Tables for Westinghouse AP600 SBLOCA, MSLB, and SGTR Scenarios, NUREG/CR-6451
J. N. Reyes Jr., L. Hochreiter, 1998, Scaling analysis for the OSU AP600 test facility (APEX), Nucl. Eng. Des., 186, 53-109
B. D. Chung, J. H. Song, S. K. Sim, W. J. Lee, J. J. Jeong., 1997, Development of Preliminary PIRT of Thermal-Hydraulic Phenomena for 330MWt SMART Integral Reactor, KAERI/TR-912/97, KAERI
G. E. Wilson, B. E. Boyack, B. D. Cheung, L. E. Hochreiter, J. N. Reyes, J. M. Cozzol, 2001, Phenomena Identification and Ranking Tabulation, KNGR LBLOCA, INEEL, WFO861702
B. D. Chung et. al., Phenomena Identification and Ranking Tabulation for APR-1400 Direct Vessel Injection Line Break, C.D. Rom, F00211, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Seoul, Korea, October 5-9, 2003
C.S. Lee, 1996, Analysis methodology for the post-trip return to power steam line break event, KAERI/TR-698/96, KAERI
W.J. Lee et. al., 2002, Development of Realistic Thermal Hydraulic System Analysis Code, KAERI/RR-2235/2001, KAERI
H. Song, K. H. Bae, 2000, Evaluation of Analytically Scaled Model of a Pressurized Water Reactor Using the RELAP5/MOD3 Computer Code, Nucl. Eng. Des., 199, pp.215-225
W. P. Baek, C. H. Song, B. J. Yun, T. S. Kwon, S. K. Moon, S. J. Lee, KAERI Integral Effect Test Program and the ATLAS Design, F00201, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Seoul, Korea, October 5-9, (2003)
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