Reactor safety analyses

Maximum Release. The analytical model described above assumes that the liquid phase is completely stagnant. While this may be true in an ideal laboratory experiment where a small sample can be kept isothermal at a specified temperature, in large scale systems where non-isothermal conditions exist, both natural convection and molecular diffusion will contribute to mass transfer. This combined effect, which is often very difficult to assess quantitatively, will result in an increase in fission-product release rate. Therefore, in making reactor safety analyses, it is desirable to be able to estimate the maximum release under all possible conditions. 

Stamps, D. W., et al., "Hydrogen-Air-Diluent Detonation Study for Nuclear Reactor Safety Analyses," Sandia National Laboratories, NUREG/CR-5525, SAND89-2398 (January 1991). 

This paper reviews data on certain thermodynamic aspects of the nonstoichiometric Pu-0 system, which may serve as a basis for use In reactor safety analysis. Emphasis Is placed on phase relationships, vaporization behavior, oxygen-potential measurements, and evaluation of pertinent thermodynamic quantities. Limited high temperature oxygen potential data obtained above the fluorite, diphasic, and sesquioxide phases In the Pu-0 system are presented. 

One of the most Important thermophysical properties of reactor fuel In reactor safety analysis Is vapor pressure, for which data are needed for temperatures above 3000 K. We have recently completed an analysis of the vapor pressure and vapor composition In equilibrium with the hypostolchiometric uranium dioxide condensed phase (1 ), and we present here a similar analysis for the plutonium/oxygen (Pu/0) system. 

Reactor safety analysis, thermodynamics of Pu-oxygen system 109-21... 

Groeneveld, D. C., and C. W. Snoek, 1986, A Comprehensive Examination of Heat Transfer Correlations Suitable for Reactor Safety Analysis, in Multiphase Science Technology 2, G. F. Hewett, J. M. Delhaye, and N. Zuber, Eds., Hemisphere, Washington, DC. (5)... 

W. L. Luyben, Use of dynamic simulation for reactor safety analysis, Comput. Chem. Eng. 40, 97-109 (2012). 

The latest safety documentation update for K-Reactor in Cold Standby is discussed in Section 4.0 of this BIO and-consists primarily of the K-Reactor Safety Analysis Report ef 3-5), the K-Reactor Technical Specifications (Ref. 3-6), and the K-Reactor Cold Standby Plan O f. 3-3). These documents provide for storage and handling of unirradiated fuel and irradiated components and storage and processing of contaminated moderator. The latest safety documentation for L-and F-Reactor Disassembly Basins is also discussed in Section 4.0 of this BIO. These documents consist mainly of the L- and P-Reactor T hnical Specifications, L-Reactor Cold Shutdown Plan, P-Area Standby Plan, and the Transfer Packages for 100-L and P Area Facilities. These documents provide for storage and handling of irradiated components. 

Savannah River Site Production Reactor Safety Analysis Report K Production Reactor. WSRC-SA-10003, Amendment 4. Westfeghouse Savannah River Company. Aiken, SC, November 8,1992. 

The safety evaluation documents that are part of the authorization basis documents for K-Reactor in Cold Standby are the K-Reactor Safety Analysis Report (SAR) and the K-Reactor Cold Standby Plan. Tliese documents and their features are discussed below. 

The plan discusses the Technical Specifications for L-Reactor in Cold Shutdown and the controls they establish. The plan also states that there is no plan to update the L-Reactor Safety Analysis Re rt (Ref 4-29) rince this BIO will provide bounding analyses of the hazards associated with the Disassembty Basin of L-Reactor in Cold Shutdown. 

In 1967, E R. Farmer of the United Kingdom proposed that the probabilities as well as consequences of potential accidents need to be estimated to assess the associated risk. Farmer used 1-131 as a surrogate for consequences. By plotting the probability and consequence of each postulated accident, one could distinguish those with high risk from those with low risk. He proposed a boundary line as a criterion for acceptable risk. Farmer s work was a conceptual breakthrough in nuclear reactor safety analysis. Farmer takes full credit as the originator and pioneer of PRA. 

Muhlestein L.D, Application of Na Concrete Reaction data to Breeder, Reactor Safety Analysis. Nuclear Safety. Vol. 25, April, 1984. 

WSRC-RP-89-383, "Savannah River Site Reactor Safety Analysis Report, K Production Reactor," July 17, 1989. 

WSRC, WSRC-SAR-RX-K, -L, -P, (WSRC-RP-89-741, -742, -743), "Savannah River Site Production Reactor Safety Analysis Report," 1989. 

Personnel with reactor safety analysis expertise for augmenting reactor emergency response teams. 

The staff noted that the SRS emergency notification list (i.e., DPSOP 287, Appendix G) and its draft replacement, 6Q12 Manual (Reference 31), which is located in the TSC Communications Center, identify affected program personnel who are called out for reactor area emergencies. This list indicates that the identified personnel have reactor safety analysis expertise and report to the TSC, which adequately addresses this restart criterion. 

Fullwood, R. and R. C. Erdman, 1974, On the Use of Leak Path Analysis in Fault Tree Construction for Fast Reactor Safety, CONF-74040I-P3. 

Mulvihill, R. J. 1966, A Probabilistic Methodology for the Safety Analysis of Nucleiir Power Reactors, USAEC report PRC-R-657, February. 

Solomon, K. D. and W. G. Kastenburg, 1985, Estimating the Planning Zones for the Shoreham Nuclear Reactor, A Review of Four Safety Analysis, Rand note N-2353-DOE September. 

The analysis of transient flows is necessary for safety analysis of nuclear reactors. Such efforts usually result in the development of large computer codes (e.g., RELAP-5, RETRAN, COBRA, TRAC). Rather than going into the details of such codes, this section gives the principles and basic models involved in the analysis. 

Yadigaroglu, G., and M. Andreani, 1989, Two Fluid Modeling of Thermal-Hydraulic Phenomena for Best Estimate LWR Safety Analysis, Proc. 4th Int. Topical Meeting on Nuclear Reactors Thermal-Hydraulics, Karlsruhe, U. Mueller, K. Rehnee, and K. Rust, Eds., Rep. NURETH-4, pp. 980-996. (3)... 

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