개선된 중성자 선원 증배법을 이용한 미임계도 평가

Subcriticality Evaluation Using the Modified Neutron Source Multiplication Method

  • 윤석균 (경희대학교 테크노공학대학 원자력공학과) ;
  • 윈나잉 (경희대학교 테크노공학대학 원자력공학과) ;
  • 김명현 (경희대학교 테크노공학대학 원자력공학과)
  • Yoon, Seok-Kyun (Department of Nuclear Engineering, Kyung-Hee University) ;
  • Naing, Win (Department of Nuclear Engineering, Kyung-Hee University) ;
  • Kim, Myung-Hyun (Department of Nuclear Engineering, Kyung-Hee University)
  • 발행 : 2007.12.31

초록

원자로의 안전성 확보를 위해 재장전 기간 동안 수행되는 노물리 시험에서 제어봉의 반응도가(reactivity worth) 산출을 위해 노심의 임계도를 측정해야 하고, 기동운전 시에도 반응도 사고를 대비하여 미임계도가 감시되어야 한다. 미임계도나 제어봉가 측정을 위한 연구가 국내외적으로 지속되어 왔으며, 최근에는 일본에서 "개선된 중성자 선원 증배법(Modified Neutron Source Multiplication Method, MNSM)"이 제안되어 기존의 중성자 선원 증배법의 한계를 극복하였다. 본 연구에서는 MNSM을 경희대 교육용원자로 AGN-201에 적용하여 미임계도를 계산하고 새로운 방법의 타당성을 평가하였다. MNSM의 적용을 위해 AGN-201 원자로에 적합한 핵자료집과 중성자수송 전산코드인 TRANSX - PARTISN 체계를 구축하였고, 유효증배계수와 중성자속(flux) 분포, 수반 중성자속(adjoint flux) 분포 등을 계산하여 제어봉위치에 따른 보정인자들을 산출하였다. 원자로의 미임계도 측정값은 $BF_3$ 비례계수관으로 측정한 중성자계수율을 사용하여 확보하였다. 연구 결과로서 MNSM을 사용하여 평가한 미임계도가 전산코드로 계산하여 얻어진 이론적인 미임계도 값에 근접하고 계산된 보정인자도 유효함을 확인하였다.

To insure nuclear reactor safety, the reactivity of control rods should be calculated by measuring the criticality of reactor core and it is regularly performed during the annual physics test period. Also, the core criticality should be monitored during the start-up operation to avoid reactivity induced accidents. Many research works on control rod reactivity measurement and subcriticality measurement have been accomplished throughout the world for decades and recently a new method named "Modified Neutron Source Multiplication Method (MNSM)" was proposed in Japan which is known to be improved overcoming limitations of traditional Neutron Source Multiplication Method (NSM). In this study, MNSM was tested in calculation of subcriticalities and in evaluation of application validity using the educational reactor in Kyung Hee University, AGN-201. For this study, a revised nuclear data library and a neutron transport code system TRANSX - PARTISN were established. Correction factors for various control rod positions were produced using the k-effective values and the corresponding flux distributions and adjoint flux distributions. Experimental values of the core criticality were obtained using the neutron count rates of the BF3 proportional counters. The results showed that the expected reactivity worth of control rods by MNSM agreed well with the theoretical values and the correction factors contributed much for this purpose.

키워드

참고문헌

  1. 서두환 외. 'TRlGA Mark-II & -III 원자로 운영', KAERI/MR-166/89, 한국원자력연구소, 1990
  2. Kim, H.; et al. 'Design characteristics and startup tests of HANARO', J. Nucl. Sci. and Tech., 1996, 33, 527 https://doi.org/10.3327/jnst.33.527
  3. 이은기 외. '경수로 미임계도 감시 기술개발', 한전전력연구원, 2005
  4. Tsuji, M.; et al. 'Subcriticality measurement by neutron source multiplication method with a fundamental mode extraction', J. Nucl. Sci. and Tech., 2003, 40, 158 https://doi.org/10.3327/jnst.40.158
  5. Greenspan, E.; 'A generalized source multiplication method', Transaction of the American Nuclear Society, 1971, 14
  6. 이원근. 'AGN-201 원자로 실험', 경희대학교, 2005
  7. Naing, W.; et al. 'The effect of neutron source distribution on subcriticality measurement of pressurized water reactors using the modified neutron source multiplication method', J. Nucl. Sci. and Tech., 2003, 40, 951 https://doi.org/10.3327/jnst.40.951
  8. Naing, W.; et al. 'Subcriticality measurement of pressurized water reactors by the modified neutron source multiplication method', J. Nucl. Sci. and Tech., 2003, 40, 983 https://doi.org/10.3327/jnst.40.983
  9. Alcouffe, R.E.; et al. 'PARTISN: A time-dependent, parallel neutral particle transport code system', LAUR-05-3925, Los Alamos National Laboratory, 2005
  10. Gil, C.S. 'KASHILL199N: A multi-group library for thermal reactor design and analysis based on ENDF/ B-', 한국원자력연구소, 2005
  11. MacFarlane, R.E. 'TRANSX 2: A code for interfacing MATXS cross-section libraries to nuclear transport codes', LA-12312-MS, Los Alamos National Laboratory, 1992