Universal system of passive heat removal from the core of a research reactor

Abstract

This pa per pres ents the re sults of an anal y sis of a uni ver sal cool ing sys tem for the core of research re ac tors built on the pas sive prin ci ple of nat u ral con vec tion. A 3-D model, tech no log ical and de sign di a grams of the re ac tor in stal la tion are pro vided, along with ex am ples of numer i cal eval u a tion of tran sients dur ing the op er a tion of the cool ing cir cuit in nor mal and emer gency modes to sub stan ti ate the pos si bil ity of us ing such a cool ing sys tem in re search reac tors of small and me dium power. The prin ci pal fea ture of the de scribed pas sive sys tem is the ab sence of not only ac tive el e ments, such as cir cu la tion pumps and shut-off and con trol valves from the cool ing cir cuit, but also of pas sive el e ments with mov ing parts, such as a check valve. The cool ing cir cuit in cludes only ves sels, pip ing and a heat exchanger. The ab sence of el e ments with me chan i cal mov ing parts can sig nif i cantly re duce the like li hood of equip ment fail ures and im prove the re li abil ity of such a cool ing sys tem while also re duc ing its cost. The ver sa til ity of the pro posed sys tem al lows it to be used for a wide range of re search re ac tor plants with var i ous ca pac i ties, which are now a days be ing de vel oped de signed to carry out pro grams in var i ous ar eas of re search and ap plied us ages re lated to nu clear tech nol o gies.

The Concept of the Heat Removal System of a High-Flux Research Reactor

“…e priority methods of functioning of the heat removal systems of the NRI under consideration are the passive principles of operation of the coolant circulation systems in the cooling circuits set out in [3,4]. e only exceptions are the core cooling circuit and the pool cooling circuit when the reactor is operating at the nominal power level.…”

Optimal design of a nuclear power plant condenser control system based on multi-objective optimization algorithm

“…The RELAP5 pro gram is a tran sient sim u la tion pro gram com monly used in nu clear power plant mod - [6,7]. The nu clear power plant con denser model es tab lished by RELAP5 pro gram can be re liable [8].…”

Approximate model for evaluation of thermal-hydraulic transients associated with rapid power increase in research nuclear reactor

“…The SN code is cou pled ki net ics and ther mal-hy drau lic code used for the MARIA re ac tor anal y ses. Its ac cu racy has been val i dated by RELAP5 Mod 3.3 [20,21].…”