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العنوان
Design and operation of nuclear power plants :
الناشر
Enshrah E.M.Ahmed,
المؤلف
Ahmed,Enshrah E.M.
هيئة الاعداد
مشرف / M.E.Nagy
مشرف / A.F.El-Saiedi
باحث / Enshrah E.M.Ahmed
مناقش / Mohamed Aly
الموضوع
nuclear power plants .
تاريخ النشر
1984 .
عدد الصفحات
i-v+246 P.;
اللغة
الإنجليزية
الدرجة
الدكتوراه
التخصص
الهندسة
تاريخ الإجازة
1/1/1984
مكان الإجازة
جامعة الاسكندريه - كلية الهندسة - Nuclear engineering
الفهرس
Only 14 pages are availabe for public view

from 291

from 291

Abstract

Loss-of-Coolant Accident (LOCA) is one of the design basis accidents that draw great attention in reactor safety stu¬dies. Protection against LOCA has long been an essential part of the defense-in-depth concept used by the nuclear industry on ~onfirming safe operation of nuclear power pl¬ants (NPPs).
Many codes have been constructed to describe the conseque¬nces of LOCA in Pressurized Water Reactors (PWR). Beca¬use of complexity and interference between the variables incorporated in LOCA, computational facility limitations, and numerical solution problems, noneof the present avail¬able codes can be considered complete.
This work presentsa physico-thermal hydraulic model which can be regarded~ complete transient analysis for the consequences of blowdown phase of a double-ended cold leg
LOCA in PWRs. The analysis is developed with the i .. f
producing a simple, relatively reliable and ef;Eii~t~e diction scheme of the evaluation of LOCA ti~~i:~ )
One of the main features of the present analY~~~t:~;;~/’ it reflects, for the first time in LOCA analys1.’&~~c):.erg1.c behind the water-hammer.
The developed hydraulic model is represented mathematically
by the two well-known quasi-linear partial differential equations which are converted to four-total differential equations by the Characteristic method and then solved nu¬merically. By this approach, analysing the entire accident sequences, including the computation of the initial condi¬tions, becomes an easy task.
Beside the hydraulic model, the analysis presents a devel¬oped heat transfer mode selection logic scheme to treat the blowdown heat transfer in PWR. A complete solution of point reactor Kinetics equations, with all heat sources encountered during the course of LOCA, is presented with the aim of getting the instantaneous effective power.
All the proposed physical models are combined together and programmed in FORTRAN IV language to form the PWRTEM code. This code was tested successfully using the results obtained i from the LOFT tests as input data. All results as well
( as conclusions and the present code planned improvements
j for future versions are presented •