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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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U.K., Japan to extend decommissioning partnership
The U.K.’s Sellafield Ltd. and Japan’s Tokyo Electric Power Company have pledge to continue to work together for up to an additional 10 years, extending a cooperative agreement begun in 2014 following the 2011 tsunami that resulted in the irreparable damage of TEPCO’s Fukushima Daiichi plant.
Kazuyoshi Miki, Kotaro Inoue
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 161-169
Technical Paper | doi.org/10.13182/NSE76-A15686
Articles are hosted by Taylor and Francis Online.
A new calculation code, the Hot Spot Probabilistic Evaluation Code (HOSPEC), is presented for evaluating hot-spot factors in a fast reactor. This code calculates the probability distribution of temperature in the whole core by means of a Monte Carlo method. Each Monte Carlo trial involves a complete thermal conduction analysis, thereby reducing errors due to assumptions in analytic procedures currently in use. With this code it is possible to determine the probability that fuel pellets, fuel pins, or subassemblies will exceed the limiting temperature, as well as determine the number of such “hot spots” that will develop. A quantitative comparison is made of the results obtained from this code with those from other analyses of a prototype fast reactor. The comparison has indicated, among other points, the following findings: 1. For zero hot spots, a conventional analytic evaluation code SHOSPA gives conservative results, i.e., ∼20°C at the fuel center, at a 3σ confidence level. 2. It is of crucial importance to take into account the temperature dependence of the properties of the materials. Neglecting such dependence leads to a much more conservative temperature prediction, e.g., ∼50°C at the fuel center.