Computer Codes and Database

The scope of studies and computer codes are summarized in Table 1.15. SRAC is a neutronic core calculation code developed by Japan Atomic Energy Agency (IAEA) [21]. FEMAXI-6 is a light water reactor fuel analysis code also developed by IAEA [31]. All other codes in the table were developed mostly by graduate students at the University of Tokyo during their thesis studies. Some codes did not have names. 

One-dimensional bum-up and two-dimensional R-Z core calculation procedures for the fast reactor are found in refs. [108,109]. The LOCA analysis code, SCRELA was described in ref. [110]. The procedure for a simplified PSA is also described there. The single channel thermal-hydrauUc calculation code SPROD, the two-dimensional coupled core calculation scheme of the thermal spectram reactor with water rods and transient and accident analysis code at supercritical-pressure, SPRAT are described in ref. [111]. 

Single channel thermal hydraulics (SPROD), 3D coupled core neutronic/thermal-hydraulic (SRAC-SPROD), Coupled subchannel analysis, Statistical thermal design method. Fuel rod behavior (FEMAXI-6), Data base of heat transfer coefficients of supercritical water (Oka-Koshizuka correlation) 

Plant system Plant heat balance and thermal efficiency Plant control 

Safety Transient and accident analysis at supercritical-and subcritrical pressure (SPRAT-F, SPRAT-DOWN), ATWS analysis (SPRAT-DOWN), LOCA analysis (SCRELA,SPRAT-DOWN-DP), Time-dependent subchannel analysis Start-up (sliding pressure and constant pressure) 

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Finding To sustain advances in chemical science and technology, new approaches and IT infrastructures are needed for the development, support, and management of computer codes and databases. 

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