[{"data":1,"prerenderedAt":-1},["ShallowReactive",2],{"detail-sidebar-cat-0-en-105":3,"doc-seo-663194-105":59,"doc-detail-663194-en":130},{"code":4,"msg":5,"data":6},0,"success",[7,13,18,23,28,33,38,43,48,51,55],{"id":8,"doc_module":4,"doc_module_name":9,"category_name":10,"show_sort_weight":11,"slug":12},1,"Document","Story & Novel",90,"story-novel",{"id":14,"doc_module":4,"doc_module_name":9,"category_name":15,"show_sort_weight":16,"slug":17},2,"Literature",80,"literature",{"id":19,"doc_module":4,"doc_module_name":9,"category_name":20,"show_sort_weight":21,"slug":22},4,"Exam",70,"exam",{"id":24,"doc_module":4,"doc_module_name":9,"category_name":25,"show_sort_weight":26,"slug":27},5,"Comic",60,"comic",{"id":29,"doc_module":4,"doc_module_name":9,"category_name":30,"show_sort_weight":31,"slug":32},6,"Technology",50,"technology",{"id":34,"doc_module":4,"doc_module_name":9,"category_name":35,"show_sort_weight":36,"slug":37},7,"Healthcare",40,"healthcare",{"id":39,"doc_module":4,"doc_module_name":9,"category_name":40,"show_sort_weight":41,"slug":42},8,"Research & Report",30,"research-report",{"id":44,"doc_module":4,"doc_module_name":9,"category_name":45,"show_sort_weight":46,"slug":47},9,"Religion & Spirituality",20,"religion-spirituality",{"id":46,"doc_module":4,"doc_module_name":9,"category_name":49,"show_sort_weight":46,"slug":50},"World Cup","world-cup",{"id":52,"doc_module":4,"doc_module_name":9,"category_name":53,"show_sort_weight":52,"slug":54},10,"Lifestyle","lifestyle",{"id":56,"doc_module":4,"doc_module_name":9,"category_name":57,"show_sort_weight":24,"slug":58},19,"General","general",{"code":4,"msg":60,"data":61},"ok",{"site_id":62,"language":63,"slug":64,"title":65,"keywords":66,"description":67,"schema_data":68,"social_meta":123,"head_meta":125,"extra_data":127,"updated_unix":129},105,"en","chapter-2-reactor-pressure-vessel-design","Chapter 2. Reactor Pressure Vessel Design","","Chapter 2 details the design requirements for a reactor pressure vessel, considering operating and emergency deviations as well as rare external events such as earthquakes and aircraft crashes. It explains how neutron irradiation affects allowable assessment regions and lists key tasks across material properties, flaw characterization, loading determination, degradation, surveillance, and worst-case assumptions. It contrasts probabilistic and deterministic safety approaches, describes crack arrest requirements, and outlines basis safety measures including redundancy, monitoring, validated codes, and optimized ingot quality. It then summarizes service conditions, including pressure, temperature, neutron irradiation, coolant, materials, and how neutron exposure is defined across countries, noting historical design-life fluence values.",{"@graph":69,"@context":122},[70,84,105],{"@type":71,"itemListElement":72},"BreadcrumbList",[73,77,79,82],{"item":74,"name":75,"@type":76,"position":8},"https://docshare.wps.com","Home","ListItem",{"item":78,"name":9,"@type":76,"position":14},"https://docshare.wps.com/document/",{"item":80,"name":40,"@type":76,"position":81},"https://docshare.wps.com/document/research-report/",3,{"item":83,"name":65,"@type":76,"position":19},"https://docshare.wps.com/document/chapter-2-reactor-pressure-vessel-design/663194/",{"url":83,"name":65,"@type":85,"image":86,"author":91,"headline":65,"publisher":94,"fileFormat":97,"inLanguage":63,"description":67,"dateModified":98,"datePublished":99,"encodingFormat":97,"isAccessibleForFree":100,"interactionStatistic":101},"DigitalDocument",{"url":87,"@type":88,"width":89,"height":90},"https://docshare.wps.com/thumbnails/chapter-2-reactor-pressure-vessel-design/663194.png","ImageObject",300,407,{"name":92,"@type":93},"Chumphorn","Person",{"url":74,"name":95,"@type":96},"DocShare","Organization","application/pdf","2026-10-29","2026-10-28",true,{"@type":102,"interactionType":103,"userInteractionCount":81},"InteractionCounter",{"@type":104},"ViewAction",{"@type":106,"mainEntity":107},"FAQPage",[108,114,118],{"name":109,"@type":110,"acceptedAnswer":111},"What events and deviations must the reactor pressure vessel design consider?","Question",{"text":112,"@type":113},"The design accounts for functional requirements under hot water (PWR) or steam (BWR), deviations from normal operation, and loads from low-probability external events such as earthquakes and aircraft crashes, as well as loading patterns from normal, emergency, and upset conditions.","Answer",{"name":115,"@type":110,"acceptedAnswer":116},"How does the chapter address neutron irradiation in the RPV assessment?",{"text":117,"@type":113},"It limits the discussion to the vessel’s core belt line where material accumulates fluence above 10^21 m^-2 (E > 1 MeV). It also notes that loading and degradation assessments must consider different exposure definitions used in different countries.",{"name":119,"@type":110,"acceptedAnswer":120},"What are the two main safety strategies described for preventing catastrophic failure?",{"text":121,"@type":113},"A probabilistic approach assumes failure under severe events with extremely low probability, while a deterministic approach defines design conditions where catastrophic failure is ruled out even under the most severe events, based on material toughness and independent redundancies.","https://schema.org",{"og:url":83,"og:type":124,"og:title":65,"og:site_name":95,"og:description":67},"article",{"robots":126,"canonical":83},"index,follow",{"doc_id":128,"site_id":62},663194,1793225731,{"code":4,"msg":5,"data":131},{"doc_id":128,"user_id":132,"nickname":92,"user_avatar":133,"doc_module":4,"category_id":39,"category_name":40,"doc_title":65,"doc_description":67,"doc_content":134,"file_id":135,"file_url":136,"file_type":137,"file_size":138,"view_count":81,"is_deleted":4,"is_public":8,"is_downloadable":8,"audit_status":8,"page_count":139,"language":140,"language_code":63,"site_id":62,"html_lang":63,"table_of_contents":141,"faqs":142,"seo_title":143,"seo_description":67,"update_tm":129,"read_time":144},2336475401981,"https://ap-avatar.wpscdn.com/avatar/22000c94efd8d5204d?x-image-process=image/resize,m_fixed,w_180,h_180&k=1786935347598174694","# Chapter 2.  Reactor Pressure Vessel Design\n\nJ.Fohl  \nStaatliche Materialprüfungsanstalt(MPA)Universitat Stuttgart,Germany  \n## 1 Introduction\n\nThe design of the RPV has to take into account all functionalrequirements to provide hot water(pressurized water reactor,PWR)or steam(boiling water reactor,BWR)and all possibledeviations from normal operating conditions as well as loadsresulting from low probability external events such asearthquake and air plane crash.  \nWith regard to neutron irradiation the discussion of RPVdesign is limited to the core belt line of the vessel,whichis defined as the region where the material accumulates afluence of more than 1021 m-2 (E >1 MeV)[1,2].However,all loading patterns resulting from normal operation,emergency and upset conditions in the plant have to beconsidered in their effect on the RPV.  \nThe design process includes a variety of different tasks.Starting with the specification of the functional parametersthe main areas are:  \n-specification of initial material properties withsufficient reserve accounting for time dependingdegradation.  \n-reliable determination of material properties and thepressure and state of flaws in the component(qualityassurance)  \n-determination of loading(operating,service)conditions  \n-time dependent degradation under service conditions  \n-surveillance of material and flaw state as well asmonitoring of service conditions  \n-assumptions for worst case conditons with respect toloading spectrum,material and flaw state.  \nFor the assessment of overall safety,validated computercodes(thermal hydraulics and finite element codes)andfracture mechanics concepts must be available to determine  \n-pressure and temperature as a function of time for allpossible and postulated events in the plant,considering the plant specific interaction ofcomponents and events  \n-loading(stress,strain)of the component for a givenpressure and temperature under steady state andtransient conditions  \n-stress intensity and strain distribution of thecomponent assuming the presence of flaws.  \nFailure of the reactor pressure vessel can be by leakage orby bursting,however,both cases have to be prevented byadequate design according to the Code requirements for boilerand pressure vessels as it is e.g.the ASME Code in the US orthe KTA-Code in Germany.Crack initiation may occur,butarrest of the crack has to be assured at a depth of 75%ofthe wall thickness[3].  \nThe likelyhood of the occurrence of an event is assumed andcan be estimated on a probabilistic basis.In consequence ofan event two different safety strategies are in current use.In the probabilistic safety approach the vessel is assumed tofail under some severe events which,however,have anextremely low probability.Alternatively,the deterministicsafety approach determines design conditions under whichcatastrophic failure is ruled out even in case of the mostsevere events.The philosophy of the deterministic approachis based on a material toughness concept with additionalindependent redundancies as outlined in the German \"BasisSafety Concept\",Fig.1,[4].The redundant measures are:  \n-\"multiple parties testing\"to assure and record theinitial quality of the component  \n-understanding of the thermo-mechanical behavior of thematerial and thus to establish the\"worst case\"material state  \n-continuous monitoring of safety-relevant“in-serviceparameters\"to assure that the design assumptionscover all events conservatively  \n-availability of validated computer codes,fracturemechanics concepts and non destructive examination(NDE)and evaluation methods.  \nThe substential prerequisite,however,for a \"basis safedesign\"is the production of an ingot with optimized chemicalcomposition regarding alloying,accompanying and traceelements including a reduced segregation pattern.Thisincorporates low sensitivity against degradation duringmanufactoring(forging,heat-treatment,welding,post weld  \nheat-treatment),provides high initial toughness and assuresa minimum of defects.Ad","cbCait27Mb5enH0b","https://ap.wps.com/l/cbCait27Mb5enH0b","pdf",682463,54,"English","# 1 Introduction\n## RPV safety philosophy and design tasks\n# 2 Service Conditions\n## Safety-relevant parameters and operating ranges\n## Materials, flaw formation, and neutron fluence","[{\"question\":\"What events and deviations must the reactor pressure vessel design consider?\",\"answer\":\"The design accounts for functional requirements under hot water (PWR) or steam (BWR), deviations from normal operation, and loads from low-probability external events such as earthquakes and aircraft crashes, as well as loading patterns from normal, emergency, and upset conditions.\"},{\"question\":\"How does the chapter address neutron irradiation in the RPV assessment?\",\"answer\":\"It limits the discussion to the vessel’s core belt line where material accumulates fluence above 10^21 m^-2 (E \\u003e 1 MeV). It also notes that loading and degradation assessments must consider different exposure definitions used in different countries.\"},{\"question\":\"What are the two main safety strategies described for preventing catastrophic failure?\",\"answer\":\"A probabilistic approach assumes failure under severe events with extremely low probability, while a deterministic approach defines design conditions where catastrophic failure is ruled out even under the most severe events, based on material toughness and independent redundancies.\"}]","Chapter 2. Reactor Pressure Vessel Design | PDF",136]