LEADER 00000cam a2200637Mi 4500 
001    on1004996470 
003    OCoLC 
005    20200417035707.1 
006    m     o  d         
007    cr cnu---unuuu 
008    170930s2016    xx      ob    001 0 eng d 
019    1004834126|a1013516862 
020    9782759819850|q(electronic book) 
020    275981985X|q(electronic book) 
020    |z9782759806690 
035    (OCoLC)1004996470|z(OCoLC)1004834126|z(OCoLC)1013516862 
040    EBLCP|beng|epn|cEBLCP|dYDX|dIDB|dN$T|dOCLCF|dOCLCQ|dCUY
       |dLOA|dZCU|dMERUC|dICG|dCOCUF|dDKC|dOCLCQ 
049    RIDW 
050  4 TK9202|b.N835 2016eb 
072  7 TEC|x009070|2bisacsh 
082 04 621.483|223 
090    TK9202|b.N835 2016eb 
100 1  Barré, Bertrand. 
245 10 Nuclear Reactor Systems :|ba Technical, Historical and 
       Dynamic Approach. 
264  1 Les Ulis :|bEDP Sciences,|c2016. 
300    1 online resource (433 pages). 
336    text|btxt|2rdacontent 
337    computer|bc|2rdamedia 
338    online resource|bcr|2rdacarrier 
340    |gpolychrome|2rdacc 
347    text file|2rdaft 
490 1  Génie Atomique Ser. 
500    5.5. Civilian fleet. 
504    Includes bibliographical references at the end of each 
       chapters and index. 
505 0  Introduction to the Nuclear Engineering books series ; 
       Authors; Contents; Foreword; References; Chapter 1. 
       Introduction; 1.1. General introduction; 1.2. The 
       ebullient beginnings; 1.2.1. Prehistory [1-10]; 1.2.2. 
       Uranium enrichment, the deus ex machina; 1.3. Bases for 
       comparison [12, 13]; 1.3.1. Fertile and fissile isotopes; 
       1.3.2. Moderators; 1.3.3. Coolants; 1.4. The driving 
       forces of selection; 1.5. Today (and tomorrow); 1.5.1. Gas
       -cooled reactors; 1.5.2. Graphite-moderated and boiling 
       water-cooled reactors RBMK; 1.5.3. Heavy water reactors 
       CANDU. 
505 8  1.5.4. Light water reactors PWR, BWR and VVER1.5.5. High 
       temperature reactors; 1.5.6. Fast breeders [14]; 1.5.7. 
       Molten salt reactors [1]; 1.6. Biotope, domination and 
       selection; 1.7. From spontaneous selection to a formalized
       process [14, 15]; 1.7.1. GIF, the Generation IV 
       International Forum; 1.7.2. INPRO, International Project 
       on Innovative Nuclear Reactors & Fuel Cycles; 1.8. Fusion;
       1.9. Conclusion; References; Chapter 2. CO2 gas cooled 
       reactors; 2.1. Introduction; 2.2. General architecture; 
       2.3. General features of graphite-moderated reactors. 
505 8  2.3.1. Fuel: natural uranium and magnesium clad (UNGG & 
       Magnox)2.3.2. Graphite moderator; 2.3.3. General physical 
       properties of graphite moderated reactors; 2.4. UNGG; 
       2.4.1. The French UNGG program; 2.4.2. St Laurent A 
       example; Caisson; Core; 2.5. Magnox; 2.6. Advanced gas 
       cooled reactor AGR; Reference; Chapter 3. RBMK (Reactor 
       Bolchoi Mochtnosti Kanali); 3.1. General; 3.2. General 
       description; Overall design; Cooling; Core; 3.3. Core 
       physics; Principle of RBMK core design; Void and density 
       effects; Instabilities; Analysis of initial RBMK control 
       rod design. 
505 8  Cavity overpressure protection system3.4. Chernobyl 
       accident; Scenario; Accident sequence and analysis; 
       Initial conditions; 3.5. Changes made to improve RBMK core
       behavior; References; Chapter 4. Heavy water moderated 
       nuclear reactors; 4.1. Introduction; 4.2. General; 4.2.1. 
       Heavy-water; 4.2.2. Natural uranium; 4.2.3. Pressure 
       tubes; 4.3. Description of a CANDU 6; 4.3.1. Reactor; 
       4.3.2. Primary system; 4.3.3. Moderator system; 4.3.4. 
       Fuel; 4.3.5. Reactivity control systems; 4.3.6. Safety 
       systems; 4.3.7. Fuel cycle; 4.3.8. The vacuum building. 
505 8  4.3.9. Difficulties and incidents in the Canadian 
       programme4.3.10. Economy; 4.4. Fuel cycle possibilities; 
       4.4.1. CANFLEX fuel; 4.4.2. Slightly enriched uranium; 
       4.4.3. Recycling of the LWR fuel; 4.4.4. Perspectives; 
       References; Appendix 1: Heavy-water production; Appendix 2
       : A Heavy-water reactor with a reactor pressure vessel; 
       Chapter 5. Nuclear marine propulsion; 5.1. Introduction; 
       5.2. Main properties required for propulsion; Electricity 
       production on land-based reactors; Navy Applications; 5.3.
       History and development; USA; USSR; UK; FRANCE; China; 
       5.4. Naval reactor development [2]. 
588 0  Print version record. 
590    eBooks on EBSCOhost|bEBSCO eBook Subscription Academic 
       Collection - North America 
650  0 Nuclear reactors.|0https://id.loc.gov/authorities/subjects
       /sh85093071 
650  7 Nuclear reactors.|2fast|0https://id.worldcat.org/fast/
       1040734 
655  4 Electronic books. 
700 1  Anzieu, Pascal. 
700 1  Lenain, Richarch. 
700 1  Thomas, Jean-Baptiste. 
776 08 |iPrint version:|aBarré, Bertrand.|tNuclear Reactor 
       Systems : A Technical, Historical and Dynamic Approach.
       |dLes Ulis : EDP Sciences, ©2016|z9782759806690 
830  0 Génie Atomique Ser. 
856 40 |uhttps://rider.idm.oclc.org/login?url=http://
       search.ebscohost.com/login.aspx?direct=true&scope=site&
       db=nlebk&AN=1605165|zOnline eBook via EBSCO. Access 
       restricted to current Rider University students, faculty, 
       and staff. 
856 42 |3Instructions for reading/downloading the EBSCO version 
       of this eBook|uhttp://guides.rider.edu/ebooks/ebsco 
901    MARCIVE 20231220 
948    |d20200422|cEBSCO|tebscoebooksacademic 3-13-4-17 3106 
       |lridw 
994    92|bRID