Translation of "the Romanian Nuclear Power Equipment Market" Report Plant Market Trends Report

Translation   of   "the   Romanian   Nuclear   Equipment   Market   Report   Plant   Market   Trends   Report,   July,   2024:
This   report   was   elaborated   on   the   basis   of   the   following   publicly   available   sources   of   information   and   documents:  
•European   Union   and   national-level   measures   and   policies   strategies   and   plans   regarding   the   energy   sector;
•European   Union   and   national-level   primary   and   secondary   legislation;
•The   latest   version   of   International   Atomic   Energy   Agency   (IAEA)   Reports   such   as   country   profiles   regarding   the   nuclear   sector;
•Commission   for   the   Control   of   Nuclear   Activities   (CNCAN)   website   for   specific   norms   and   regulations   in   the   nuclear   sector;
•Nuclearelectrica   National   Company   (SNN)   annual   report   2023   and   SNN’s   official   website
•Public   Procurement   Electronic   System   (SEAP)   database   for   SNN’s   acquisition   contracts   for   nuclear   equipment;
•Nuclearelectrica   Supplier   Guide;
•ROMATOM   website;
•D&B   Hoovers   databases   for   company   information;
•National   Bank   of   Romania   (NBR)   database   for   exchange   rates   on   FOREX   market;  
•National   Energy   Regulatory   Authority   (ANRE)   market   monitoring   reports   for   a   market   share   overview   of   energy   producers;
•Press   releases   in   the   Romanian   (nuclear)   energy   sector.

Translation of the Indian Nuclear Power Plant Market Trends Report

Translate   the   following   Report:
Nuclear   Power   Industry   of   India   –   South   Korean   Business   Perspective   -,  
Dr.   Varun   Hassija,   Prof.   Suneet   Singh
Department   of   Energy   Science   and
Engineering,   IIT   Bombay,   India.

Preparation of Test Operation Administrative Guides for KJRR

1.   Prepare   the   Test   Operation   Plans   for   KJRR
2.   Prepare   the   Test   Administrative   Procedures   for   KJRR

Gap Analysis of RG 1.105

1.   Analyze   the   design   impact   by   comparing   and   evaluating   the   revised   contents   of   RG   1.105,   “Setpoints   for   Safety-Related   Instrumentation,”   Rev.   4,   with   those   currently   applied   to   the   design,   Rev.   3.
2.   Compare   and   evaluate   the   differences   between   the   2018   revised   edition   of   ISA   67.04.01,   “Setpoints   for   Nuclear   Safety-Related   Instrumentation,”   and   the   1994   revised   edition.

Development of NAPS Design Requirements for ARA Research Reactor

1.   Development   of   Design   Requirements   for   Control   Element   Assembly   Application   Program  
2.   Development   of   Design   Requirements   for   Xenon   Reactivity   Calculation   Program
3.   Development   of   Design   Requirements   for   In-Core   Instrument   Signal   Processing   Program
4.   Development   of   Design   Requirements   for   Offline   Core   monitoring   Code   Data   Collection   Program
5.   Development   of   Design   Requirements   for   Update   Time   Dependent   Variables   Program

Development of Design Concept for Microreactor Nuclear Power Plant

In   this   research,   we   developed   a   design   concept   for   a   micro   nuclear   power   plant   (named   MicroX)   with   the   following   characteristics   and   presented   a   general   arrangement   (GA)   concept   that   houses   both   the   reactor   system   and   power   conversion   system   within   a   20-foot   container.

-   Core   thermal   output   of   4.5   MWt   with   cycle   length   of   7   years
-   Fuel   compacts   using   UCO   kernel   TRISO   particles
-   Graphite   (moderator)   fuel   blocks   housing   the   fuel   compacts
-   Development   of   heat   pipe-cooled   reactor   core   design
-   Development   of   heat   pipe   performance   evaluation   program
-   High-efficiency   power   conversion   system   using   supercritical   carbon   dioxide   (CO2)   Brayton   cycle
-   Application   of   Turbine-Alternator-Compressor   (TAC)   unit   for   miniaturization   and   simplification
-   Miniaturization   through   the   use   of   highly   Integrated   Printed   Circuit   Heat   Exchanger   (PCHE)   for   precoolers   and   recuperation

Development of Design Concept of SMR Reactor Assembly for the Propulsion of High Speed Ultra Large Ship

1.   Determination   of   the   reactor   thermal   power   based   on   analysis   of   trends   in   ultra-large   container   ships

2.   Nuclear   fuel   and   core   design
      -   Development   of   nuclear   fuel   and   control   rod   design   concepts
      -   Establishment   of   design   requirements   and   core   design   concepts
      -   Evaluation   of   nuclear   fuel   temperature   reserves

3.   Setting   fluid   system   design   values
      -   Primary   system   design   variables
      -   Secondary   system   design   variables

4.   Development   of   nuclear   reactor   assembly   design   concepts
      -   Concept   of   nuclear   fuel   support   and   control   rod   guidance   design
      -   Design   concepts   for   major   components   such   as   the   control   element   drive   mechanism,   main   cooling   pump,   and   steam   generator  

5.   Analysis   of   the   potential   economic   feasibility   of   nuclear-powered   container   ships