 
              Concept of a Future 
  High Pressure - Boiling Water Reactor, HP-BWR
               Frigyes Reisch 
  Nuclear Power Safety, KTH Royal Institute of Technology 
  Stockholm, Sweden
              Abstract
               Some four hundred Boiling Water Reactors (BWR)
                and Pressurized Water Reactors (PWR) have been in operation for
                several decades. The present concept, the High Pressure Boiling
                Water Reactor (HP-BWR) makes use of the operating experiences.
                HP-BWR combines the advantages and leaves out the disadvantages
                of the traditional BWRs and PWRs by taking in consideration the
                experiences gained during their operation. The best parts of
                the two traditional reactor types are used and the troublesome
                components are left out. The HP-BWR major benefits are; 
               1. Safety is improved; -Gravity
                operated control rods -Large space for the cross formed control
                rods between fuel boxes -Bottom of the reactor vessel without
                numerous control rod penetrations -All the pipe connections to
                the reactor vessel are well above the top of the reactor core
                -Core spray is not needed -Internal circulation pumps to assure
                hydrodynamic stability. 
               2. Environment friendly; -Improved
                thermal efficiency, feeding the turbine with ~340 0C (15 MPa)
                steam instead of ~285 0C (7MPa) -Less warm water release to the
                recipient and less uranium consumption per produced kWh 
               3. Cost effective, simple; -Direct
                cycle, no need for complicated steam generators -Moisture separators
                and steam dryers are inside the vessel and secondary separators
                and dryers can be installed outside the reactor vessel, inside
                or outside the containment -Simple dry containment 
              1.	Introduction
              Now the time has come to move a step further
                and develop an improved type of power reactors. Common sense,
                public confidence and economic considerations demand that this
                new design should not be a big leap from the presently functioning
                machines, however it should be a significant improvement. Therefore
                it is important to avoid those parts of the older designs which
                caused trouble in the past e.g. PWR steam generators, BWR perforated
                reactor vessel bottoms and instead rely only on a stable construction
                with proven components which served well in the past. The High
                Pressure – Boiling Water Reactor (HP-BWR) attains these
                goals, by using the PWR; pressure vessel, the electro-magnetic
                control rod operator and the BWR; core internals, circulation
                pumps and steam and moisture separators. 
                
              Figure 1. The High Pressure Boiling Water Reactor 
               2.	Safety is improved
              The control rods are gravity operated as this
                system served well in PWRs. However here the form is like a cross,
                as it is in the BWRs. This assures large space for the cross
                formed rods between the BWR type fuel boxes. 
                
  Figure 2. Reactor vessel head and reactor internals 
               The bottom of the reactor vessel now is without
                numerous control rod penetrations a great advantage compared
                with the previous design 
                
  Figure 3. The bottom of the reactor vessel and circulation pumps  
              All the pipe connections to the reactor vessel
                are well above the top of the reactor core. This means that a
                pipe break would not empty the reactor vessel. Therefore core
                spray is not needed. 
               Internal circulation pumps are used to assure
                hydrodynamic stability. This way the orifices at the fuel channel
                inlets are chosen so that the one phase pressure drop will dominate
                over the two phase pressure drop to avoid hydrodynamic oscillations.
                By applying natural circulation one could omit the circulation
                pumps, however the margin to avoid hydrodynamic oscillations
                would be diminished. 
              Compared with the traditional BWR the HP-BWR
                has further advantages; 
                
  Table 1. Comparison between BWR and HP-BWR  
              due to the high temperature, improved thermal
                efficiency and due to the increased negative power reactivity
                coefficient further improved inherent stability. 
                
  Figure 4. Long term stability without the use of any control system. 
  Inherently stable reactor 
              3. Environment friendly
               Improved thermal efficiency is assured by feeding
                the turbine with ~340°C (15.5MPa) steam instead of ~285°C
                (7MPa). The Carnot cycle theoretical efficiency (THot -
                TCold )/ THot is for BWR ~46% and for HP-BWR
                ~51% at TCold = 300 K. This demonstrate the advantage
                of the HP-BWR which utilizes the fuel more efficiently and releases
                less warm cooling water to the environment per produced kWh  
              4.	Cost effective, simple
              The HP-BWR operates in direct cycle mode, no
                need for complicated and expensive PWR steam generators and the
                very complicated BWR reactor pressure vessel bottom. Moisture
                separators and steam dryers are inside the pressure vessel and
                secondary separators and dryers can be installed outside the
                reactor vessel, inside or outside the containment. The containment
                is a simple dry containment which allows easy entrance and inspections
                and also minor repairs during operation. 
                
  Figure 5: HP-BWR in a dry containment 
              5.	Acknowledgements
              Thanks to Hernan Tinoco of the Forsmark NPP and Joanna Peltonen
                of KTH for their valuable support. 
               
  6.	Reference
              ENS
                  News, October 2007, Proceedings of the European Nuclear
              Conference (ENC) 2007, Brussels 
               
              
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