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RISS 인기검색어
- 검색키워드
- 저자 : V. Jagannathan (검색결과 3 건)
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V. Jagannathan,U. Pal,R. Karthikeyan,A. Srivastava,S. A. Khan 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Nuclear data plays a vital role in the design of nuclear power reactors, especially for new conceptual ones where adequate validation base does not exist. For the continuity of ssion nuclear power beyond the present day power reactors operated in an open cycle mode, it is necessary to explore the possibility of reactor designs with higher conversion, rather higher breeding potential. In this context two reactor designs in the thermal and fast spectrum have been conceived having the above desired characteristics. The thermal version called `A Thorium Breeder Reactor' (ATBR) has conversion ratio higher by about 55% compared to an LWR [1]. The fast version called the `Fast Thorium Breeder Reactor' (FTBR) considers internal blanket or fissile breeding zones and hence has a reasonably high breeding ratio of at least 1.25 [2]. In this paper we present the variations in the salient physical core characteristics of the thermal version for three different sets of nuclear data libraries based on ENDFB/VI.8, ENDFB/VII and JEFF3.1 datasets [3].
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Need for High Temperature Nuclear Data Library for LWR Design Computations
Suhail Ahmad Khan,V. JAGANNATHAN,Usha Pal,R. Karthikeyan,Argala Srivastava 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
WIMS Library Update Project (WLUP) was taken up by the IAEA for updating the nuclear cross section data libraries. The 172 group WIMS libraries (45 fast, 47 resonance groups and 80 thermal) obtained under WLUP are used for reactor physics computations. These libraries have cross section data for 173 nuclides up to ^(244)Cm. Resonance Integral Tabulation (RIT) data for 28 resonant nuclides are provided for a set of background cross sections and temperature values up to 1100 ˚K. In the reactor design computations, one requires simulation of reactor states with fuel temperatures reaching nearly up to melting point of 2800 ℃ for UO_2 fuel. While using deterministic codes for high temperature calculation beyond 1100 ˚K, a linear extrapolation w.r.t. √T_(fuel) is normally done. This is not quite satisfactory since even a small error in the slope near the highest temperature of 1100 ˚K data point could lead to significant error if the extrapolation is done up to very high temperatures. Recently an updated WIMS library has become available through WLUP follow up activities. This library contains RIT data for 48 resonant nuclides including several minor actinides and temperature extended up to 2500 ˚K and burnup chain has been extended up to ^(252)Cf. Use of the new library has alleviated the problem of possible error in extrapolation. The new library called `HTEMPLIB' has been tested for the design computations of VVER-1000 MWe reactor being constructed at Kudankulam, Tamilnadu, India. Two fuel types containing 4% and 3.6% enriched fuel were analyzed using the hexagonal lattice burnup code EXCEL. The results of the lattice analyses with the new WIMS library as well as the original WIMS library `JEFF31GX', containing data up to a temperature of 1100 ˚K are presented in this paper.
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DEVELOPMENT AND VALIDATION OF COUPLED DYNAMICS CODE 'TRIKIN' FOR VVER REACTORS
Obaidurrahman, K.,Doshi, J.B.,Jain, R.P.,Jagannathan, V. Korean Nuclear Society 2010 Nuclear Engineering and Technology Vol.42 No.3
New generation nuclear reactors are designed using advanced safety analysis methods. A thorough understanding of different interacting physical phenomena is necessary to avoid underestimation and overestimation of consequences of off-normal transients in the reactor safety analysis results. This feature requires a multiphysics reactor simulation model. In this context, a coupled dynamics model based on a multiphysics formulation is developed indigenously for the transient analysis of large pressurized VVER reactors. Major simplifications are employed in the model by making several assumptions based on the physics of individual phenomenon. Space and time grids are optimized to minimize the computational bulk. The capability of the model is demonstrated by solving a series of international (AER) benchmark problems for VVER reactors. The developed model was used to analyze a number of reactivity transients that are likely to occur in VVER reactors.
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