CN1044547A - Improve the method for reliability of embrittlement monitoring for nuclear pressure vessel - Google Patents

Improve the method for reliability of embrittlement monitoring for nuclear pressure vessel Download PDF

Info

Publication number
CN1044547A
CN1044547A CN89100546A CN89100546A CN1044547A CN 1044547 A CN1044547 A CN 1044547A CN 89100546 A CN89100546 A CN 89100546A CN 89100546 A CN89100546 A CN 89100546A CN 1044547 A CN1044547 A CN 1044547A
Authority
CN
China
Prior art keywords
sample
monitoring
pressure vessel
embrittlement
length
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Withdrawn
Application number
CN89100546A
Other languages
Chinese (zh)
Other versions
CN1018215B (en
Inventor
史耀武
张新平
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Xian Jiaotong University
Original Assignee
Xian Jiaotong University
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Xian Jiaotong University filed Critical Xian Jiaotong University
Priority to CN89100546A priority Critical patent/CN1018215B/en
Publication of CN1044547A publication Critical patent/CN1044547A/en
Publication of CN1018215B publication Critical patent/CN1018215B/en
Expired legal-status Critical Current

Links

Images

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Sampling And Sample Adjustment (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)

Abstract

The present invention discloses a kind of method that improves reliability of embrittlement monitoring for nuclear pressure vessel, belongs to nuclear reactor safety technical research field.The sample that the present invention used monitoring test is through improvement and design, with the method for electron beam welding.Make but shellfish size sample of eight new prefabricating fatigue cracks at last.Can only obtain one to three toughness data by a common sample and be increased to nine, be equivalent under the constant prerequisite of pressure vessel inner cavity size, the quantity of fracture toughness monitoring sample is increased by three to nine times, can significantly improve the reliability of embrittlement monitoring for nuclear pressure vessel.

Description

Improve the method for reliability of embrittlement monitoring for nuclear pressure vessel
The invention belongs to nuclear reactor safety technical research field, is a kind of method that improves nuclear reactor pressure container neutron irradiation reliability of embrittlement monitoring.
Reactor pressure vessel is understood because of the neutron damage embrittlement in operational process, thereby shortens the serviceable life of pressure vessel.A large amount of small size samples of for this reason in reactor vessel, will packing into, for its in whole 30 years to 40 years designed life, can periodically take out sample come the monitoring pressure container rigidity can degeneration.Because the restriction of the bulk of nuclear reactor pressure container inner chamber preciousness, what put in the past mostly is conventional stretching and impact specimen (ASTM E185-82).In recent years, state such as Great Britain and America has also begun to adopt the Charpy bay of prefabricating fatigue crack and the variation (ASTM E636-83) that compact tensile specimen is come monitoring reaction heap pressure vessel fracture toughness in operational process.
In order from the sample material that stands neutron irradiation, to obtain more information, be beneficial to the optimum operation design of nuclear pressure vessel, to test with the sample of mistake in addition second development and utilization caused people's attention (Mc Connel, P.et al.ASTM STP888,1986), these methods mainly contain: the 1. standard V-notch Charpy impact test specimen crossed of neutron irradiation, after impulse test is finished, weld two cramp bars with the arc stud welding method respectively at the half sample two ends of thrusting, the sample spreading is arrived standard length, thereby form a new impact specimen; The half sample spreading that thrusts after also can adopting the mechanical connection method to test also constitutes a new standard impact specimen.If cross the fracture toughness of material through prefabricating fatigue crack also energy measurement neutron irradiation.Be 2. the half Charpy bay that thrusts to be pressed into special anchor clamps in addition, and through prefabricating fatigue crack, thereby a new compact tensile specimen obtained.Adopt above-mentioned these methods a common sample can only be able to be obtained toughness test data and be increased to three.
Because the method for little radiation test block being made large-sized composite sample by welding has also been introduced in the restriction of reactor pressure vessel inner cavity size in ASTM E636-83.For example, make compact tension specimen composite sample and dynamically tear composite sample.
The objective of the invention is, on the previous work basis, embrittlement is monitored that sample redesigns with the prefabricating fatigue crack Charpy bay of crossing, can only obtain one to three toughness data from a sample and bring up to nine fracture toughness test data of acquisition, so just can be greatly improved and increase the reliability of fracture toughness assessment.
Ultimate principle of the present invention is:
The prefabricating fatigue crack of process neutron irradiation is shellfish size monitoring sample but, after through quasistatic or dynamic three point bending test, can obtain a toughness data, then test be carried out line cutting five equilibrium with two half Charpy bays crossing with superfine molybdenum filament and be processed into eight sections.Adopt the high-energy-density welding method to connect cramp bar respectively in the both sides of each section to recover the standard length size of Charpy bay, so just constituted eight new but shellfish size composite samples, center section is the material that neutron irradiation is crossed, and two ends are the cramp bar material.Show that through repetition test the cramp bar material should be steel for welded structures, its strength level does not all have influence than radiative material intensity high or low 20%.Adopt the vacuum electron beam welding method of high-energy-density can significantly reduce the heat affecting scope of sweating heat radiation to middle material.When the width of radiative material was 5mm in the middle of in the design, weld heating did not influence the test findings of this but shellfish composite sample.
Below in conjunction with accompanying drawing invention is further described:
The location of sample each several part and clamping when Fig. 1 is electron beam welding.
Fig. 2 is the but shellfish size composite sample newly that has been welded into.
The prefabricating fatigue crack of process neutron irradiation is shellfish size sample but, after through quasistatic or dynamic three point bending test, test is carried out line cutting with two half Charpy bays crossing with the molybdenum filament of diameter 0.12mm, becoming length is the eight equal parts segment of 5.5mm, and sectional area still is 10 * 10mm 2; The sample two ends that with above-mentioned length are 5.5mm are 5mm through grinding.The cramp bar material is the nuclear pressure vessel steel such as A508CI3 steel without radiation, and being processed into sectional area is 10 * 10mm 2, length is 25mm.The new but shellfish composite sample center section that constitutes is that length is the material that the Radiation monitoring test of 5mm was used, and two ends are the cramp bar material.With reference to accompanying drawing 1, with length is the material segment (1) and the two supports bar (2) of the radiation of 5mm, go up the location at custom-designed anchor clamps (3) and (3 '), clamping is fixed, and on vacuum electron beam welder the material segment (1) of radiation and cramp bar (2) is coupled together with the method for welding then.The weld seam (4) of two electron beam weldings has been shown in the accompanying drawing 2.The but shellfish size composite sample warp cutting processing breach that welds, prefabricating fatigue crack, reprocessing side channel, thereby make but shellfish size composite sample of eight new prefabricating fatigue cracks, such one but shellfish size composite sample can obtain nine toughness data.
Advantage of the present invention is:
A Charpy bay can only obtain one to three toughness data in the world at present, adopts the but shellfish size composite sample of foregoing invention design, can obtain the toughness data of nine good reproducibilities.Repetition test shows its coefficient of variation or relative standard deviation in 3%, and the Weibull distribution slope is all greater than 20, thereby significantly improves the reliability of the neutron irradiation embrittlement monitoring of nuclear pressure vessel.
Best implementation condition of the present invention is:
The cramp bar material should be without the A508CI3 steel of radiation or A533B equal pressure container welded structural steel; During electron-bombardment welding, cramp bar (2) the end face end face that material segment (1) is crossed in radiation with center section wants bright and clean and vertical with the length direction of composite sample; In order to reduce the width of welding joint, must adopt the vacuum electron beam welding method of high-energy-density; For further reduce heat effect and welding deformation but the shellfish composite sample should in anchor clamps (3) that purple steel is made and (3 '), finish welding process; When reducing welding heat effect and anchor clamps (3) and (3 ') be repeatedly used consideration, it is the best that anchor clamps (3) and (3 ') material select red copper; The but shellfish composite sample surface that is welded into does not need to carry out any surface working again, can process side channel at last directly at composite sample center machining gap and prefabricating fatigue crack.

Claims (2)

1, a kind of method that improves reliability of embrittlement monitoring for nuclear pressure vessel, the test of neutron irradiation embrittlement monitoring is welded last two cramp bars (2) respectively with the two ends of a bit of (1) of the sample of crossing, the sample spreading is arrived standard length, again at the centre machining gap, prefabricating fatigue crack, the reprocessing side channel, form a new sample, can only obtain fracture toughness test data by a common sample is increased to several, feature of the present invention is through but shellfish size sample of the prefabricating fatigue crack of neutron irradiation by one, through line cutting and grinding, make eight identical segments (1), every segment two ends electro-beam welding method, the cramp bar of burn-oning (2), make but shellfish size sample of eight new prefabricating fatigue cracks thus, can obtain nine fracture toughness test data.
2, by the described a kind of method that improves reliability of embrittlement monitoring for nuclear pressure vessel of claim 1, it is characterized in that one through but shellfish size sample of the prefabricating fatigue crack of neutron irradiation, molybdenum filament with diameter 0.12mm carries out the line cutting, cutting into length is eight identical segments of 5.5mm, each length be the segment two ends of 5.5mm through grinding, become the segment that length is 5mm (1); Cramp bar (2) material is the nuclear pressure vessel steel without radiation, and sectional area is 10 * 10mm 2, length is 25mm; With length is two cramp bars (2) of the segment (1) of 5mm together with two ends, fixes at red copper clamp (3) and (3 ') last clamping, welds with electron beam welding machine.
CN89100546A 1989-01-23 1989-01-23 Method of improving reliability of embrittlement monitoring for nuclear pressure vessel Expired CN1018215B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN89100546A CN1018215B (en) 1989-01-23 1989-01-23 Method of improving reliability of embrittlement monitoring for nuclear pressure vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN89100546A CN1018215B (en) 1989-01-23 1989-01-23 Method of improving reliability of embrittlement monitoring for nuclear pressure vessel

Publications (2)

Publication Number Publication Date
CN1044547A true CN1044547A (en) 1990-08-08
CN1018215B CN1018215B (en) 1992-09-09

Family

ID=4853914

Family Applications (1)

Application Number Title Priority Date Filing Date
CN89100546A Expired CN1018215B (en) 1989-01-23 1989-01-23 Method of improving reliability of embrittlement monitoring for nuclear pressure vessel

Country Status (1)

Country Link
CN (1) CN1018215B (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101206929B (en) * 2006-12-14 2012-03-28 韩电Kps株式会社 Inspection apparatus for reactor bottom mounting type device nozzle
CN103870679A (en) * 2014-02-24 2014-06-18 苏州热工研究院有限公司 Judgment method for minimum inserting section size in Charpy impact test sample recombination technology
CN107803605A (en) * 2017-09-28 2018-03-16 中国航发动力股份有限公司 A kind of weld jig of multilayer thin-wall annular part laser circumference seam weld

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101206929B (en) * 2006-12-14 2012-03-28 韩电Kps株式会社 Inspection apparatus for reactor bottom mounting type device nozzle
CN103870679A (en) * 2014-02-24 2014-06-18 苏州热工研究院有限公司 Judgment method for minimum inserting section size in Charpy impact test sample recombination technology
CN107803605A (en) * 2017-09-28 2018-03-16 中国航发动力股份有限公司 A kind of weld jig of multilayer thin-wall annular part laser circumference seam weld

Also Published As

Publication number Publication date
CN1018215B (en) 1992-09-09

Similar Documents

Publication Publication Date Title
CN1044547A (en) Improve the method for reliability of embrittlement monitoring for nuclear pressure vessel
RajaKumar et al. Microstructure and Mechanical properties of Borated Stainless Steel (304B) GTA and SMA welds
CN105127557B (en) The medicine core gas shielded arc welding Rework Technics of marine engineering large thick steel plate under low temperature environment
Horn et al. Fatigue behaviour of T-joints improved by TIG dressing
Chen et al. The effects of simultaneous overload and spot heating on crack growth retardation in fatigue
Savage et al. Hydrogen-assisted cracking in HY-130 weldments
Bacher et al. Brazing of niobium to stainless steel for UHV applications in superconducting cavities
Rajamani et al. Parameter optimization and properties of friction welded quenched and tempered steel
Salleh et al. Improvement of mechanical properties in treated spot welded joint
Tang et al. Friction stir welding–an advanced approach to repair nuclear power plant components
ZHOU et al. Numerical simulation of welding deformation in weld on thin low carbon steel plate
Sanusi et al. Mechanical Characterization of Welded AISI 304L Stainless Steel Using Tungsten Inert Gas (TIG) and Manual Metal Arc (MMA) Welding Processes
Klueh et al. Elevated temperature tensile behaviour of ERNiCr-3 weld metal
Asano et al. Thick plate welding of irradiated stainless steel
Sample et al. Liquid metal embrittlement susceptibility of welded MANET II (DIN 1.4914) in liquid Pb-17Li.
SU873017A1 (en) Method of testing joint for crack formation resistance in fusion area
Cioroagă et al. EFFECT OF WELDING CURRENT INTENSITY ON TENSILE STRENGTH OF PRESSURE VESSEL STEEL SUBMERGED WELDED JOINTS
Ramdani et al. Comparison of penetration depth based on effect of DCEP and DCEN polarity on SMAW process using E6013 with ASTM A36
Kasatkin et al. Study of the Conditions of Transverse Crack Formation in the Welding of 14 Kh 2 GMR Steel
Sharma et al. Failure of a high strength low alloy steel pressure chamber
Trevisan et al. Fracture modes and acoustic emission characteristics of hydrogen-assisted cracking in high-strength low-alloy steel weldment
UMEKUNI et al. Application of Undermatched Welds for High-Strength and Heavy-Section Steels
Almqvist et al. The influence of impurity elements on the embrittlement of ferritic weld metals
Holbert Jr et al. Welding of a powder metallurgy uranium alloy
Piatti et al. Time-independent mechanical properties of a chromium-manganese austenitic steel weldment

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C13 Decision
GR02 Examined patent application
C14 Grant of patent or utility model
GR01 Patent grant
C19 Lapse of patent right due to non-payment of the annual fee
CF01 Termination of patent right due to non-payment of annual fee