CN105390166A - dual cooling nuclear fuel rod with tolerance for the loss of a coolant accident - Google Patents

dual cooling nuclear fuel rod with tolerance for the loss of a coolant accident Download PDF

Info

Publication number
CN105390166A
CN105390166A CN201510520328.0A CN201510520328A CN105390166A CN 105390166 A CN105390166 A CN 105390166A CN 201510520328 A CN201510520328 A CN 201510520328A CN 105390166 A CN105390166 A CN 105390166A
Authority
CN
China
Prior art keywords
cladding tubes
interior cladding
described interior
thickness
fuel rod
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.)
Granted
Application number
CN201510520328.0A
Other languages
Chinese (zh)
Other versions
CN105390166B (en
Inventor
金亨奎
金铉佶
梁宰豪
金健湜
金宰勇
李康禧
李荣镐
尹庆镐
姜兴硕
丘阳铉
宋根禹
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.)
Korea Atomic Energy Research Institute KAERI
Original Assignee
Korea Atomic Energy Research Institute KAERI
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 Korea Atomic Energy Research Institute KAERI filed Critical Korea Atomic Energy Research Institute KAERI
Publication of CN105390166A publication Critical patent/CN105390166A/en
Application granted granted Critical
Publication of CN105390166B publication Critical patent/CN105390166B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/16—Details of the construction within the casing
    • G21C3/18—Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C16/00—Alloys based on zirconium
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/324—Coats or envelopes for the bundles
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Disclosed is a dual cooling nuclear fuel rod with tolerance for the loss of a coolant accident. The dual cooling nuclear fuel rod includes an external coating pipe which is in the shape of a hollow cylinder, and has a circular cross section in a longitudinal direction; and an inner coating pipe which is in the shape of a hollow cylinder, has a smaller diameter than the external coating pipe, is located in a hollow part of the external coating pipe, prevents plastic deformation in a normal condition, has a thickness for generating elastic buckling before generating ballooning deformation in the external coating pipe in the event of a coolant loss accident.

Description

The two cold nuclear fuel rod of anti-refrigerant leaks accident
Technical field
The present invention relates to two cold (dual-cooled) nuclear fuel rod of anti-refrigerant leaks accident (loss-of-coolant), more particularly, the present invention relates to the two cold nuclear fuel rod of thickness by adjusting involucrum (cladding) pipe in two cold nuclear fuel rod and tolerance expansion fault (ballooningfailure) when refrigerant leaks accident occurs.
Background technology
Nuclear safety means that protection individual, the public and environment do not suffer to produce the radioactive ray from nuclear facilities, and is the nuclear engineering field of peaceful utilization of atomic energy absolute demand.Nuclear energy power generation is at the energy source that major industrialized country is important always since over half a century, and now, nearly 400 nuclear power stations in the whole world are in operation.Same in Korea S, from 1978, nuclear energy power generation continued to rise with economic development, covered now more than 30% of Korea S's generating total amount.Like this, along with the increase of nuclear power station, the concern of nuclear safety and specification and importance are increased.Especially, after the Fukushima nuclear accident occurred on March 11st, 2011, the concern of the safety of nuclear energy power generation facility is increased, and attention nuclear reactor and nuclear fuel with security-related problem more.
Whether the safety analysis of nuclear power station reaches the security evaluating nuclear power station design by the permissible criterion of the various design basis accidents guaranteeing legal provisions according to the design of nuclear power station.In addition, in order to ensure security and the operability of nuclear power station, provide the design of protection system and security system with the information (performance constraint condition, security system setting value etc.) needed for regulations for technical operation.When the excessive operation condition expected except normal operating condition, the safety shutdown of nuclear reactor should be guaranteed.In addition, for the refrigerant leaks accident (LOCA) as design basis accident (DBAs), devise the security system of such as emergency core (core) cooling system (ECCS) etc. and perform safety analysis.Thus, the possibility substantially preventing core melt down accident has been made an effort.
Design basis accident refer to the design phase consider hypothetical accident to guarantee the security function corresponding with each operating conditions of power house, and comprise elementary (initial) event, such as overload, device damage, operating personnel's error and the disaster that may occur in power house.Here, should be by the function of the security system guaranteed, first, maintain the integrality (integrity) of the coolant pressure restriction in nuclear reactor, second, safety shutdown nuclear reactor also maintains this safety shut-off state, the 3rd, Accident prevention or slow down accident and make the amount of the radiomaterial be discharged in environment be no more than statutory restrictions.
When above-mentioned refrigerant leaks accident occurs, what make coolant flow path due to the dilatational strain caused by internal pressure increase in typical tubular nuclear fuel rod forms interruption, therefore following problem may be there is: when Emergency Cooling System performs the water spray for cooling nuclear reactor, nuclear fuel rod may be not sufficiently cooled.Fig. 1 shows in the shape by using the expansion observed in the experiment of the cladding tubes of nuclear fuel rod simulation refrigerant leaks accident to damage in commercial light-water reactor.
Thus, needing before commercialization, by the two cold nuclear fuel rod of current development being designed to anti-accident, providing a kind of safer nuclear fuel rod.
Summary of the invention
Embodiments of the present invention aim to provide a kind of two cold nuclear fuel rod of anti-refrigerant leaks accident, to make under refrigerant leaks accident conditions cladding tubes outside make interior cladding tubes elastic buckling can occur before expanding.
Embodiments of the present invention also aim to provide a kind of two cold nuclear fuel rod of anti-refrigerant leaks accident, and it comprises the interior cladding tubes that plastic yield can not occur in the normal operation period.
According to an aspect of the present invention, provide a kind of two cold nuclear fuel rod of anti-refrigerant leaks accident, described two cold nuclear fuel rod comprises: outsourcing package, and described outsourcing package is the hollow tube-shape longitudinally with round section; With interior cladding tubes, described interior cladding tubes is the hollow tube-shape that diameter is less than the diameter of described outsourcing package, described interior cladding tubes is positioned at the hollow bulb of described outsourcing package, the not plastic yield in the normal operation period of interior cladding tubes, and described interior cladding tubes has the thickness allowing described interior cladding tubes generation elastic buckling when refrigerant leaks accident occurs before described outsourcing package expands distortion; And pellet, pellet is charged space between outsourcing package and interior cladding tubes and by nuclear fission produce power.
According to a further aspect in the invention, provide a kind of two cold nuclear fuel rod, described two cold nuclear fuel rod comprises: outsourcing package, and described outsourcing package is the hollow tube-shape longitudinally with round section; Interior cladding tubes, described interior cladding tubes is the hollow tube-shape that diameter is less than the diameter of described outsourcing package, and described interior cladding tubes is positioned at the hollow bulb of described outsourcing package; And pellet, described pellet is charged the space between described outsourcing package and described interior cladding tubes, and via nuclear fission produce power, wherein, the thickness of described interior cladding tubes is less than the thickness tb of described interior cladding tubes when there is elastic buckling, and the thickness of described interior cladding tubes is greater than the thickness ta of described interior cladding tubes when expanding.
Accompanying drawing explanation
From the detailed description below in conjunction with accompanying drawing, above and other object of the present invention, other advantage of characteristic sum will be more clearly understood, in the accompanying drawings:
Fig. 1 shows the figure of the shape of the expansion damage that typical fuel rod occurs in refrigerant leaks accident;
Fig. 2 shows the figure of two cold nuclear fuel rod according to the embodiment of the present invention; And
Fig. 3 shows the figure of the elastic buckling phenomenon of the interior cladding tubes of two cold nuclear fuel rod according to the embodiment of the present invention.
Embodiment
Below, embodiments of the present invention are described in detail with reference to the accompanying drawings.First, it should be noted that in the Reference numeral of the element of each figure provided, even if when identity element is illustrated in various figures, same Reference numeral also refers to identity element.In addition, in explanation of the present invention, because known structure or function can not fuzzy the understanding of the present invention, therefore known structure or function can not be described in detail.
Fig. 2 shows the figure of two cold nuclear fuel rod according to the embodiment of the present invention, and shows the cross section of two cold nuclear fuel rod.
With reference to Fig. 2, two cold nuclear fuel rod comprises outsourcing package 70 and interior cladding tubes 30.In addition, with reference to (b) of Fig. 2, inner space 51 can be limited between interior cladding tubes 30 and outsourcing package 70.Pellet (pellet) 50 is charged inner space 51 and is used as two cold nuclear fuel rod ((a) see Fig. 2).
First, the structure of two cold nuclear fuel rod will be described in detail.Outsourcing package 70 is the hollow tube-shape longitudinally with round section, and interior cladding tubes 30 is less than the hollow tube-shape of the diameter of outsourcing package 70 for diameter and is positioned at the hollow bulb of outsourcing package 70.In addition, pellet 50 is charged the space limited between outsourcing package 70 and interior cladding tubes 30, and by nuclear fission produce power.Here, outsourcing package 70 is designed to have such thickness: this thickness makes bending deformation (bucklingdeformation) can not occur during the normal running that nuclear accident does not occur.
Then, by describe in detail in the normal operation period with refrigerant leaks accident during the structure of two cold nuclear fuel rod.In the normal operation period, in interior cladding tubes 30, tensile stress (tensilestress) is produced.This is due to following former resulting phenomenon: in the normal operation period, in two cold nuclear fuel rod, the inside 10 of cladding tubes maintains about 15MPa reactor coolant, the pressure of the inside 10 of interior cladding tubes is greater than the gas exerts that produced by the nuclear fission of the burnup according to pellet 50 pressure to the outside of interior cladding tubes 30.
On the contrary, when refrigerant leaks accident occurs, compression stress (compressivestress) in interior cladding tubes 30, is produced.This is due to following former resulting phenomenon: when the inside 10 of interior cladding tubes drop to atmospheric pressure, and the pressure of the inside 10 of interior cladding tubes is less than the gas exerts that produced by the nuclear fission of the burnup according to pellet 50 pressure to the outside of interior cladding tubes 30.Thus, be understandable that, when refrigerant leaks accident occurs, according to the thickness of interior cladding tubes 30, elastic buckling may occur.
Although the external pressure of outsourcing package 70 also maintains the about 15MPa being equivalent to reactor coolant pressure in the normal operation period, when refrigerant leaks accident occurs, this pressure breakdown is to atmospheric pressure.Therefore, when refrigerant leaks accident occurs, inflated configuration may be produced in cladding tubes outside according to the thickness of outsourcing package.Thus, in order to prevent the swelling of outsourcing package 70, needing the thickness of interior cladding tubes 30 to be set to and make: interior cladding tubes 30 can cladding tubes 70 first flexing before expanding phenomenon outside.The thickness that the present invention relates to internal cladding tubes designs, to prevent the swelling of the outsourcing package when refrigerant leaks accident occurs.
As above-mentioned, the thickness of interior cladding tubes 30 should be set to make fully: once there is refrigerant leaks accident, and interior cladding tubes 30 can cladding tubes 70 first flexing before expanding phenomenon outside.More specifically, interior cladding tubes 30 has the thickness larger than the thickness of the dilatational strain that interior cladding tubes 30 occurs, there is not the plastic yield of interior cladding tubes 30 in the normal operation period, interior cladding tubes 30 also has and starts the little thickness of the thickness of flexing than the interior cladding tubes when refrigerant leaks fault occurs.
Now, use mathematical equation is illustrated the present invention.Here, the pressure as the load causing the distortion of interior cladding tubes or outsourcing package is defined as follows.Here, owing to the present invention relates to the distortion of interior cladding tubes, therefore will the position of the pressure of interior cladding tubes be applied to as benchmark.The outside of interior cladding tubes is corresponding with the inside that there is pellet of two cold nuclear fuel rod, and is the region that the pressure of the gas produced by the nuclear fission of the burnup according to pellet is applied to.This with corresponding relative to the outside of interior cladding tubes, and is represented as p here 0.In the normal operation period, the pressure of the inside of interior cladding tubes becomes the pressure of the reactor coolant pressure of about 15MPa, and becomes atmospheric pressure when refrigerant leaks accident occurs, and these two pressure are denoted respectively as p i, normaland p i, LOCA.
When interior cladding tubes 30 to be out of shape owing to internal pressure expand outwardly (expand) time, the thickness of interior cladding tubes can be obtained by user's formula 1.
[equation 1]
σ θ θ = p r t
Wherein, σ θ θbe the stress when cladding tubes is expanded in circumference, p is the internal pressure of expansion cladding tubes, and r and t is radius and the thickness of cladding tubes respectively.
By user's formula 1, when expanding when the internal pressure owing to interior cladding tubes 30, can by the thickness using the equation 2 being derived from equation 1 to obtain interior cladding tubes.
[equation 2]
t a r = p σ y s = p i , n o r m a l - p o σ y s
Wherein, t abe the thickness of interior cladding tubes when this expansion takes place, r is the radius of interior cladding tubes, and p is the internal pressure of cladding tubes in expansion, σ ysthe yield strength of the material of interior cladding tubes, p othe pressure that the pressure of the gas produced by the nuclear fission of the burnup according to pellet 50 is in the normal operation period applied to interior cladding tubes, and p i, normalbe the pressure of the chilled water in nuclear reactor, it is corresponding with the about 15MPa existed in the inside 10 of interior cladding tubes during normal running.
By contrast, when there is elastic buckling in interior cladding tubes 30, can by the thickness using following equation 3 to obtain interior cladding tubes 30.
[equation 3]
p c r = E 4 ( 1 - ν 2 ) ( t r ) 3
By user's formula 3, when there is elastic buckling in interior cladding tubes 30, can by the thickness using the equation 4 being derived from equation 3 to obtain interior cladding tubes 30.
[equation 4]
t b r = 4 ( 1 - ν ) 2 p c r E 3 = 4 ( 1 - ν 2 ) ( p o - p i , L O C A ) E 3
Wherein, t bbe the thickness of the interior cladding tubes when elastic buckling occurs, r is the radius of interior cladding tubes, and ν is the Poisson ratio of interior cladding tubes, p crbe the critical buckling pressure when interior cladding tubes subsides (collapsed), E is the elastic modulus of the material of interior cladding tubes, p o-p i, LOCAbe the pressure of the gas produced by the nuclear fission of the burnup according to pellet 50 be applied to the outside of interior cladding tubes 30 pressure and when refrigerant leaks accident occurs interior cladding tubes inside 10 in difference between the pressure (atmospheric pressure) that exists.
Consider each definite value used in equation 2 and equation 4, in the zircaloy situation of the versatile material as cladding tubes, due to σ ysbe the value of 1000MPa or less, E is the value being greater than 100000MPa, and ν has the positive number that maximal value is 0.5, is therefore appreciated that the value of the rightmost value in equation 2 and the root in equation 4 is all less than 1.Therefore, for cladding tubes in same radius, the thickness meeting the cladding tubes of equation 4 is always greater than the thickness of the cladding tubes meeting equation 2.That is, the thickness t of cladding tubes in when elastic buckling occurs balways be greater than the thickness t of interior cladding tubes when this expansion takes place a.Therefore, when determining the thickness not allowing elastic buckling occurs, the plastic yield caused by internal pressure can not be there is.
Thus, when the thickness t of cladding tubes in two cold nuclear fuel rod satisfies condition t b>t>t atime, the integrality during normal running is maintained, and in interior cladding tubes 30, flexing occurs, thus prevent the dilatational strain of outsourcing package 70 when refrigerant leaks accident occurs.
Below, the present invention will be illustrated in greater detail by embodiment.But the embodiment below illustrated is not used in and limits the scope of the invention, but only for illustration of the present invention.
For two cold nuclear fuel rod, consider there is the outsourcing package of 15.9mm external diameter and there is the interior cladding tubes of 9.5mm external diameter.Here, the material constant of cladding tubes (Zry-4 of 350 DEG C) is identical with table 1, think that the cooling pressure of nuclear reactor is 15.5MPa during normal running, the internal pressure of the fuel rod of the pressure of the gas produced as the nuclear fission by the burnup according to pellet is assumed to be 0MPa to 5MPa (0MPa is used for tensioning circumference stress (tensilehoopstress), and 5MPa is used for the elastic buckling of interior cladding tubes).
[table 1]
By using the size of two cold nuclear fuel rod and material constant and equation 1, the thickness t of the interior cladding tubes when not expanding can be obtained a.That is, calculating is worked as time, due to t a>=0.213mm, result, when the thickness of interior cladding tubes is 0.22mm or larger, is appreciated that and can not expands distortion in normal state.
Therefore, when the thickness of interior cladding tubes is 0.25mm, can obtain by user's formula 3 pressure that elastic buckling occurs as follows.
p c r = 70140.36 4 ( 1 - 0.25 2 ) ( 0.25 4.625 ) = 2.594 M P a
Thus, when there is refrigerant leaks accident, if compared with excellent internal pressure, the internal pressure landing of nuclear reactor produces the pressure differential of 2.6Mpa or larger, then in interior cladding tubes, elastic buckling phenomenon occurs.
When in when supposing in interior cladding tubes flexing, the shape of cladding tubes is fully compressed into as shown in (a) of Fig. 3, the change of interior area of section before and after the flexing of interior cladding tubes 30 of two cold nuclear fuel rod can be obtained as follows.The interior area of section of the two cold nuclear fuel rod before flexing is identical with equation 5, and the interior area of section of the two cold nuclear fuel rod after flexing is identical with equation 6.
[equation 5]
A o = π { ( r i o ) 2 - ( r o i ) 2 } = π { 7.08 2 - 4.75 2 } = 86.59 mm 2
Wherein, A othe interior area of section of two cold nuclear fuel rod when cladding tubes is intact in before being generation elastic buckling, the inside radius of outsourcing package, it is the external radius of interior cladding tubes.
[equation 6]
A f = π ( r i o ) 2 - 2 l t = π × 7.08 2 - 2 × 14.42 * ) × 0.25 = 150.27 mm 2
Wherein, A fbe the interior area of section of two cold nuclear fuel rod when there is elastic buckling in interior cladding tubes, t is the thickness of interior cladding tubes.In addition, when being deformed into the tabular of the thickness of the twice of the thickness with interior cladding tubes when supposing the cross section of cladding tubes in bobbin shape to be compressed completely by elastic buckling, the width of l display plate.That is, l can obtain from following equation 7.
[equation 7]
2 πr o i = 2 l + 4 t
Therefore, by calculating (150.27-86.59)/86.59, can obtain the two internal volume increment rate of cold fuel rod before and after flexing is 73.5%.Therefore, pressure can reduce about 58%.
That is, when there is flexing in interior cladding tubes 30, the rapid pressure landing caused due to the increase of the internal volume of generation based on fuel rod, the power therefore expanding outwardly outsourcing package also reduces.Therefore, distortion can not be expanded in outsourcing package.But, when flexing occurs reality in interior cladding tubes, expect that interior cladding tubes can not be fully compressed owing to the interference with pellet.Therefore hereinafter with reference to Fig. 3, this situation is described.
Fig. 3 shows the figure of the elastic buckling phenomenon of the interior cladding tubes of two cold nuclear fuel rod according to the embodiment of the present invention.(a) of Fig. 3 shows interior cladding tubes 30 by situation about flattening completely, and (b) of Fig. 3 shows interior cladding tubes 30 and do not flattened completely but combine the possible distortion with the interference of pellet.
More specifically, when there is flexing in cladding tubes 30 in reality, owing to the interference of uranium ring pellet with the hardness more much bigger than the hardness of cladding tubes, the semicircle occurred as shown in (b) of Fig. 3 or crescent are out of shape, instead of the shape flattened completely as shown in (a) of Fig. 3.Now, when there is the distortion as shown in (b) of Fig. 3, the volume increase of fuel rod inside may become less than the situation of (a) of Fig. 3.Therefore, the amount of pressure breakdown may reduce.But, due to flatten completely compared with shape ((a) of Fig. 3) and interior stream can be formed in addition, therefore anti-accident in can obtain good effect.
According to theme of the present invention, the two cold nuclear fuel rod of anti-refrigerant leaks accident maintains integrality in the normal operation period, and in allowing when there is refrigerant leaks accident, cladding tubes subsides, and thus can prevent the dilatational strain of outsourcing package.Thus, the anti-accident of two cold nuclear fuel rod can be increased.In addition, when interior cladding tubes subsides, the volume between interior cladding tubes and outsourcing package increases, and the internal pressure of nuclear fuel rod reduces.Meanwhile, the allowance (margin) that prevents the expansion of outsourcing package from damaging becomes large, and making it possible to be provided under refrigerant leaks accident can the two cold nuclear fuel rod of long term maintenance safe condition.
Although be explained above preferred implementation, this instructions is not limited to above-mentioned particular implementation.Those skilled in the art can make various modification when not departing from the spirit and scope of claim.And these modification should not be understood as that the spirit and scope independent of the present invention's design.

Claims (9)

1. a two cold nuclear fuel rod for anti-refrigerant leaks accident, described two cold nuclear fuel rod comprises:
Outsourcing package, described outsourcing package is the hollow tube-shape longitudinally with round section; With
Interior cladding tubes, described interior cladding tubes is the hollow tube-shape that diameter is less than the diameter of described outsourcing package, described interior cladding tubes is positioned at the hollow bulb of described outsourcing package, and described interior cladding tubes has the thickness allowing described interior cladding tubes generation elastic buckling when refrigerant leaks accident occurs before described outsourcing package expands distortion.
2. the two cold nuclear fuel rod of anti-refrigerant leaks accident according to claim 1, is characterized in that,
Described interior cladding tubes has the thickness of the thickness be greater than when described interior cladding tubes expands distortion.
3. the two cold nuclear fuel rod of anti-refrigerant leaks accident according to claim 1, is characterized in that,
The thickness of described interior cladding tubes when described interior cladding tubes expands is obtained by using following equation:
t a r = p σ y s = p i , n o r m a l - p o σ y s
Wherein, t abe the thickness of described interior cladding tubes when this expansion takes place, r is the radius of described interior cladding tubes, and p is the internal pressure expanding described interior cladding tubes, σ ysthe yield strength of the material of described interior cladding tubes, p othe gaseous tension being applied to described interior cladding tubes owing to pellet burnup during normal running, and p i, normalthe reactor coolant pressure of described interior cladding inner during being normal running.
4. the two cold nuclear fuel rod of anti-refrigerant leaks accident according to claim 1, is characterized in that,
The thickness of described interior cladding tubes when described interior cladding tubes generation elastic buckling can be obtained by using following equation,
t b r = 4 ( 1 - ν 2 ) p c r E 3 = 4 ( 1 - ν 2 ) ( p o - p i , L O C A ) E 3
Wherein, t bbe the thickness of the described interior cladding tubes when elastic buckling occurs, r is the radius of described interior cladding tubes, and ν is the Poisson ratio of described interior cladding tubes, p crbe the critical buckling pressure when described interior cladding tubes subsides, E is the elastic modulus of the material of described interior cladding tubes, p o-p i, LOCAby the difference be applied between the gaseous tension of described interior cladding tubes and the atmospheric pressure that the inside of described interior cladding tubes occurs when refrigerant leaks accident occurs owing to pellet burnup.
5. the two cold nuclear fuel rod of anti-refrigerant leaks accident according to claim 1, is characterized in that, the material of described outsourcing package and described interior cladding tubes is zircaloy.
6. the two cold nuclear fuel rod of anti-refrigerant leaks accident according to claim 1, is characterized in that,
When described interior cladding tubes generation elastic buckling, the shape of described interior cladding tubes not by the shape flattened completely, but is deformed into the predetermined portions making the interior stream maintaining described two cold nuclear fuel rod.
7. the two cold nuclear fuel rod of anti-refrigerant leaks accident according to claim 6, is characterized in that,
Described interior cladding tubes becomes semicircle or crescent by described distortion.
8. the two cold nuclear fuel rod of anti-refrigerant leaks accident according to claim 1, is characterized in that,
The thickness of described interior cladding tubes is less than the thickness (t of described interior cladding tubes when there is elastic buckling b), and the thickness of described interior cladding tubes is greater than the thickness (t of described interior cladding tubes when expanding a).
9. a two cold nuclear fuel rod for anti-refrigerant leaks accident, described two cold nuclear fuel rod comprises:
Outsourcing package, described outsourcing package is the hollow tube-shape longitudinally with round section;
Interior cladding tubes, described interior cladding tubes is the hollow tube-shape that diameter is less than the diameter of described outsourcing package, and described interior cladding tubes is positioned at the hollow bulb of described outsourcing package; With
Pellet, described pellet is charged the space between described outsourcing package and described interior cladding tubes, and via nuclear fission produce power,
Wherein, the thickness of described interior cladding tubes is less than the thickness (t of described interior cladding tubes when there is elastic buckling b), and the thickness of described interior cladding tubes is greater than the thickness (t of described interior cladding tubes when expanding a).
CN201510520328.0A 2014-08-22 2015-08-21 Double cold nuclear fuel rods of anti-cooling agent leakage accident Active CN105390166B (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
KR10-2014-0109485 2014-08-22
KR1020140109485A KR101565429B1 (en) 2014-08-22 2014-08-22 A dual-cooled annular nuclear fuel rod tolerant for the loss of coolant accident

Publications (2)

Publication Number Publication Date
CN105390166A true CN105390166A (en) 2016-03-09
CN105390166B CN105390166B (en) 2017-08-22

Family

ID=54600207

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201510520328.0A Active CN105390166B (en) 2014-08-22 2015-08-21 Double cold nuclear fuel rods of anti-cooling agent leakage accident

Country Status (2)

Country Link
KR (1) KR101565429B1 (en)
CN (1) CN105390166B (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106601311A (en) * 2016-12-29 2017-04-26 华北电力大学 Nuclear fuel element
CN109036591A (en) * 2017-06-08 2018-12-18 中广核工程有限公司 Nuclear reactor
US11501717B2 (en) 2017-10-27 2022-11-15 Lg Display Co., Ltd. Gate driver that outputs gate voltage based on different signals and display device including the same

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105469838B (en) * 2015-12-23 2018-01-05 中广核研究院有限公司 Fuel assembly and its fuel rod for improving nuclear reactor safety

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20100135452A1 (en) * 2006-10-16 2010-06-03 Korea Atomic Energy Research Institute Liquid-metal-cooled fast reactor core comprising nuclear fuel assembly with nuclear fuel rods with varying fuel cladding thickness in each of the reactor core regions
CN102354539A (en) * 2011-09-15 2012-02-15 西安交通大学 Annular fuel element and annular fuel supercritical water reactor
WO2013017621A1 (en) * 2011-08-01 2013-02-07 Commissariat à l'énergie atomique et aux énergies alternatives Improved multilayer tube made from ceramic-matrix composite material, the resulting nuclear fuel cladding and associated production methods
CN103106929A (en) * 2013-02-04 2013-05-15 中国核动力研究设计院 Improved annular fuel element of supercritical water reactor and fuel component consisting of fuel element

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20100135452A1 (en) * 2006-10-16 2010-06-03 Korea Atomic Energy Research Institute Liquid-metal-cooled fast reactor core comprising nuclear fuel assembly with nuclear fuel rods with varying fuel cladding thickness in each of the reactor core regions
WO2013017621A1 (en) * 2011-08-01 2013-02-07 Commissariat à l'énergie atomique et aux énergies alternatives Improved multilayer tube made from ceramic-matrix composite material, the resulting nuclear fuel cladding and associated production methods
CN102354539A (en) * 2011-09-15 2012-02-15 西安交通大学 Annular fuel element and annular fuel supercritical water reactor
CN103106929A (en) * 2013-02-04 2013-05-15 中国核动力研究设计院 Improved annular fuel element of supercritical water reactor and fuel component consisting of fuel element

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106601311A (en) * 2016-12-29 2017-04-26 华北电力大学 Nuclear fuel element
CN106601311B (en) * 2016-12-29 2018-07-24 华北电力大学 A kind of nuclear fuel element
CN109036591A (en) * 2017-06-08 2018-12-18 中广核工程有限公司 Nuclear reactor
CN109036591B (en) * 2017-06-08 2021-10-15 中广核工程有限公司 Nuclear reactor core
US11501717B2 (en) 2017-10-27 2022-11-15 Lg Display Co., Ltd. Gate driver that outputs gate voltage based on different signals and display device including the same

Also Published As

Publication number Publication date
CN105390166B (en) 2017-08-22
KR101565429B1 (en) 2015-11-04

Similar Documents

Publication Publication Date Title
CN105390166A (en) dual cooling nuclear fuel rod with tolerance for the loss of a coolant accident
Kim A study on the grid-to-rod fretting wear-induced fuel failure observed in the 16× 16KOFA fuel
Ahn et al. Deterministic and risk-informed approaches for safety analysis of advanced reactors: Part I, deterministic approaches
Sapra et al. Design and development of innovative passive valves for Nuclear Power Plant applications
Kral Analysis and Implementation of Design Extension Conditions (DEC) at Czech NPPS and Contribution of DEC to Enhancement of Defense-In-Depth
McDowell et al. High Temperature Gas Reactors: Assessment of Applicable Codes and Standards
Bui et al. Evaluation of VVER-1200/V-491 Reactor Pressure Vessel integrity during large break LOCA along with SBO using MELCOR 1.8. 6
Kang et al. Comparison of Unavailability between Different Types of Reactors
Jung et al. FACAPT–Failure Assessment Program for CANDU Pressure Tube
CN112906201B (en) Design method for loop system overpressure protection in pressurized water reactor operation state
Riemke et al. RELAP5-3D Code for Supercritical-Pressure Light-Water-Cooled Reactors
Todreas et al. Flexible conversion ratio fast reactor systems evaluation
Cho et al. Development of PSA audit guideline and regulatory PSA model for SMART
Moisseytsev et al. NEUP Final Report: Analysis of Thermal Transients for a Sodium-CO2 Heat Exchanger
Abe et al. Development and application of modified fuel performance code based on stainless steel as cladding under steady state, transient and accident conditions
Kim et al. Environmental Envelope of SBLOCA for Wolsong Unit 1 Environmental Qualification
Lee et al. Analysis of the ATLAS SGTR-HL-05 Experiment using SPACE Code
Koh Preliminary Evaluation of Interfacing System Loss of Coolant Accident for OPR1000
Ihn et al. Failure pressure investigation in PWR rector primary coolant piping
Shin et al. An Assessment for A Filtered Containment Venting Strategy Using Decision Tree Models
Li et al. Analysis on ultimate load capacity of cylinder with local discontinuity under high temperature gradient
Schneider et al. An Advanced RCP Seal Design for Coping With Extended Loss of AC Power Event
Nistor-Vlad et al. Comparison between RELAP/SCDAPSIM/MOD3. 4 and MOD3. 6+ in Simulating a CANDU6 SBO
Kim et al. LBLOCA accident analysis for Wolsong unit 1 environmental qualification
Choi et al. Evaluation of Safety Parameters for the Deformation of CANDU Fuel Channels

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant