JPS5894677A - Steam-leakage suppressing apparatus for main steam stop valve - Google Patents

Steam-leakage suppressing apparatus for main steam stop valve

Info

Publication number
JPS5894677A
JPS5894677A JP56190535A JP19053581A JPS5894677A JP S5894677 A JPS5894677 A JP S5894677A JP 56190535 A JP56190535 A JP 56190535A JP 19053581 A JP19053581 A JP 19053581A JP S5894677 A JPS5894677 A JP S5894677A
Authority
JP
Japan
Prior art keywords
main steam
water
isolation valve
closed
pipe
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.)
Pending
Application number
JP56190535A
Other languages
Japanese (ja)
Inventor
Masahide Nishio
西尾 正英
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.)
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Tokyo Shibaura Electric Co Ltd
Nippon Atomic Industry Group Co Ltd
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 Toshiba Corp, Nippon Genshiryoku Jigyo KK, Tokyo Shibaura Electric Co Ltd, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP56190535A priority Critical patent/JPS5894677A/en
Publication of JPS5894677A publication Critical patent/JPS5894677A/en
Pending legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Lift Valve (AREA)

Abstract

PURPOSE:To prevent leakage of steam at the time when main steam stop valves are closed, by connecting a water feeding means to the part of a main steam pipe located on the upstream side of the main steam stop valves for feeding water to the main steam pipe when the main steam stop valves are closed, to such an extent that the part where a poppet and the body of the main steam stop valves are held in contact with each other can be sealed by water. CONSTITUTION:While a nuclear reactor is operated normally, a water stop valve 21 is closed and both of main steam stop valves 5, 6 are opened. On the other hand, in case that a main steam pipe 9 is damaged at a position 10 located on the side of a turbine, the main steam stop valves 5, 6 are both closed and a water stop valve 22 is opened to feed water from a pressure water source 20 via a water feed pipe 22 to the part of a main steam pipe 7 located upstreams of the first main steam stop valve 5 and to thereby effect water sealing at the region where a poppet 18 and the body 17 of the valve are held in contact with each other. With such an arrangement, it is enabled to prevent leakage of steam from the main steam stop valves 5, 6 by the function of sealing water.

Description

【発明の詳細な説明】 発明の技術分野 本発明は沸騰水形原子力発電プラントの主蒸気管破断時
に、主蒸気隔離弁のシートによるシール性を増し、主蒸
気漏洩全抑制する装置に関する。
DETAILED DESCRIPTION OF THE INVENTION Technical Field of the Invention The present invention relates to a device for completely suppressing main steam leakage by increasing the sealing performance of a main steam isolation valve seat when a main steam pipe of a boiling water nuclear power plant breaks.

発明の技術的背景 沸騰水形原子力発電プラントにおいては、第1図に示す
ように、原子炉圧力容器(1)の甲に炉水(2)が入っ
ており、その中VC炉心(3)が水没している。
Technical Background of the Invention In a boiling water nuclear power plant, as shown in Figure 1, reactor water (2) is contained in the shell of a reactor pressure vessel (1), and a VC reactor core (3) is inside the reactor water (2). It's submerged.

原子炉通常運転中は、この炉心(3)内に含1れるウラ
ニウム原子が核分裂を起こし、熱を発生する。
During normal operation of the nuclear reactor, uranium atoms contained within the reactor core (3) undergo nuclear fission and generate heat.

この熱により炉水(21は沸騰し、蒸気を発生する。This heat causes the reactor water (21) to boil and generate steam.

この蒸気は約70気圧あり、原子炉出力容器(1)の空
間部(4)を通り、主蒸気隔離弁(5)、(6)によっ
て区分される主蒸気管(1) 、 +8) 、 191
を通って、以下図示しないタービンに達し、タービンの
羽を回し、発電機を運転するようにしている。
This steam has a pressure of about 70 atmospheres, passes through the space (4) of the reactor power vessel (1), and enters the main steam pipe (1), +8), 191, which is divided by the main steam isolation valves (5), (6).
It passes through it and reaches a turbine (not shown below), which turns the blades of the turbine and operates the generator.

炉心(3)の甲の燃料棒(図示せず)の燃料ベレットは
、通常ジルカロイ被覆管に包まれており、原子炉運転中
に核分裂によって生じる放射性物質は、その中に閉じ込
められるようにしである。しかし炉心(3)中に数多く
ある燃料棒の中には、ジルカロイ被ffi、管に微小な
損傷が生じているものかある可能性があり、原子炉通常
運転中は、この微小な損傷を通して燃料ペレット中の放
射性wJ質が炉水(2)中へ漏洩し、炉水(2)が放射
能汚染されている可能性がある。
The fuel pellets of the fuel rods (not shown) in the upper part of the reactor core (3) are usually wrapped in a Zircaloy cladding tube, so that radioactive materials produced by nuclear fission during reactor operation are confined therein. . However, among the many fuel rods in the reactor core (3), there is a possibility that there may be slight damage to the Zircaloy-covered ffi and tubes, and during normal reactor operation, fuel can be removed through this minute damage. There is a possibility that the radioactive wJ substance in the pellets leaks into the reactor water (2), and the reactor water (2) is contaminated with radioactivity.

原子炉圧力容器(1)から第1の主蒸気隔離弁(5)捷
での主蒸気管(力と、第1、第2の主蒸気隔離弁(5)
(6)間の主蒸気管(8)とは劇宸設計となっており、
破断は晋辿考えられないが、第2の主蒸気隔離弁(6)
からタービン寄りの主蒸気管(9)は、原子炉通常運転
時において、何らかの原因により破断することかあり得
る。もしこのタービン寄9の主蒸気’ef (91が破
断すると、蒸気は破断口(10から激しく流出する。そ
うすると原子炉圧力容器(1)内圧力が低下するため、
燃料棒の被覆管VC微小でも損傷があった場合、燃料棒
内の放射性物質が炉水(2)中に吹き出てくる。これが
、破断口から放出されると、公衆に太きン2被曝叶をも
たら′rため、主蒸気隔離弁(5)(6)が設けらハ、
ており、主蒸気’# (91の破断を検知すると、約5
秒間で閉鎖するようにしてらる。従ってこの主蒸気隔離
弁(5)、(6)は低漏洩率であることが敗しく要求さ
れる。
Main steam pipe (power) at the junction from the reactor pressure vessel (1) to the first main steam isolation valve (5) and the first and second main steam isolation valves (5)
The main steam pipe (8) between (6) and (8) have a dramatic design,
Although the rupture is unlikely, the second main steam isolation valve (6)
The main steam pipe (9) closer to the turbine may break for some reason during normal operation of the reactor. If the main steam 'ef (91) of this turbine port 9 is ruptured, the steam will violently flow out from the rupture port (10).Then, the pressure inside the reactor pressure vessel (1) will decrease,
If there is even slight damage to the cladding tube VC of a fuel rod, radioactive materials within the fuel rod will blow out into the reactor water (2). If this is released from the fracture, it will expose the public to a large amount of radiation, so main steam isolation valves (5) and (6) are installed.
When the main steam '# (91) breakage is detected, approximately 5
It will close in seconds. Therefore, the main steam isolation valves (5) and (6) are required to have a low leakage rate.

背景技術の問題点 ところで主蒸気隔離弁は、営内流体が面一の蒸気でめ4
+ため、液体と比べ、ノートVCよる/−ルπ+を10
0≠41伍実にすることは技術的PC難しい。これ全図
面によって説明する。第2図は主蒸気隔離弁(5+ 、
 (6)の立面図で、第3図および渠4図は共に主蒸気
隔離弁閉時における第2図中のAの部分全拡大した断面
図であり、第3図は流体(11)が蒸気の場合、第4図
は水の場合全示している。これらの図において、(12
1は操作部、0四は1駆動部、0ルはボンネット、(1
5)ハ入ロ側ポデー、(I61は出口側ボデー、(17
)はボデー、f181Uポペットである。しかして水は
蒸気に比べ、その物理的性質は、はるかに高密度であり
、高粘性を有している。このため、第3図に示したよう
に蒸気からなる流体0υは、ポペット(IgJとボデー
圓との接触しているシート面のわずかな隙間から、容易
に漏洩する可能性があり、さらにシート面に微細なごみ
が付着するなどしてその密着性が損われると、許容限度
以上の漏洩を来た丁恐れがあるのに対し、第4図に示し
たように水の場合は漏洩しにくい。しかしながら、従来
の主蒸気隔離弁(5)、(6)には蒸気だけが供給され
ていたので、主蒸気隔離弁f51 、 (61から多量
に蒸気が漏洩する恐れがあった。
Problems with the Background Art By the way, the main steam isolation valve is designed so that the internal fluid is flush with steam.
+, compared to liquid, /-le π+ according to notebook VC is 10
It is technically difficult to make 0≠415. This will be explained with reference to all the drawings. Figure 2 shows the main steam isolation valve (5+,
In the elevation view of (6), both Fig. 3 and conduit Fig. 4 are fully enlarged sectional views of the part A in Fig. 2 when the main steam isolation valve is closed, and Fig. 3 is a fully enlarged cross-sectional view of the part A in Fig. 2 when the main steam isolation valve is closed. In the case of steam, FIG. 4 is fully shown in the case of water. In these figures, (12
1 is the operating section, 04 is the 1 drive section, 0 is the bonnet, (1
5) Inlet side body, (I61 is outlet side body, (17
) is the body, f181U poppet. However, the physical properties of water are much higher density and higher viscosity than steam. Therefore, as shown in Fig. 3, the fluid 0υ consisting of steam may easily leak from the slight gap between the seat surface where the poppet (IgJ and the body circle are in contact), and furthermore, If the adhesion is impaired due to the adhesion of fine dust to the water, there is a risk of leakage exceeding the allowable limit, whereas water is less likely to leak as shown in Figure 4. Since only steam was supplied to the conventional main steam isolation valves (5) and (6), there was a risk that a large amount of steam would leak from the main steam isolation valves f51 and (61).

発明の目的 本発明の目的は主蒸気隔離弁の蒸気漏洩防止性能′fr
、艮好にした主蒸気隔離弁の蒸気漏洩抑制装置全提供す
ることにある。
Object of the invention The object of the invention is to improve the steam leakage prevention performance of the main steam isolation valve.
The purpose of the present invention is to provide a fully designed main steam isolation valve steam leakage suppression device.

発明の概要 本発明においては、主蒸気隔離弁より上流側の主蒸気管
に、主蒸気隔離弁閉鎖時にその主蒸気隔離弁のポペット
とボデーの接@部を水封する程度に水金注入する水注入
装置を接続することにより、主蒸気隔離弁閉鎖時の蒸気
漏洩を防止する。
Summary of the Invention In the present invention, water-gold is injected into the main steam pipe upstream of the main steam isolation valve to the extent that the contact area between the poppet and the body of the main steam isolation valve is water-sealed when the main steam isolation valve is closed. By connecting a water injection device, steam leakage is prevented when the main steam isolation valve is closed.

発明の実施例 以下、本発明の一実施例について、第5図を参照して説
明する。この実施例においては、原子炉圧力容器(1)
の中に炉水(2)が入っており、その中に炉心(3)が
水没しており、蒸気が原子炉圧力容器(1)の空間部(
4)から、第2図ないしm4図に示す主蒸気隔離弁(5
) 、 (6)によって区分される主蒸気管(7)。
Embodiment of the Invention Hereinafter, an embodiment of the present invention will be described with reference to FIG. In this example, the reactor pressure vessel (1)
Reactor water (2) is contained in the reactor water (2), the reactor core (3) is submerged in water, and steam flows into the space (1) of the reactor pressure vessel (1).
4) to the main steam isolation valve (5) shown in Figures 2 to m4.
), (6) main steam pipe (7).

18+ 、 (91’r通ってタービンに達するように
したこと迄は従米通りであるが、第1の主蒸気隔離弁(
5)より七(Ar側の主蒸気管(力に、主蒸気隔離弁(
Fil 、 (6)閉鎖時にその主蒸気隔離弁(51、
(6)のポペット0樽とボデー07)の接触部を水封す
る程度に水を注入する圧力水源(21)に接続された注
水隔離弁Qυ付注水配管固からなる水注入装置■濁を接
続することに特徴を有する。上記圧力水源(20は図示
しないタンクに貯えた清浄水(タービン系統の復水で可
)全ポンプでカロ圧することにより簡単に得られる。
18+, (The first main steam isolation valve (
5) From 7 (main steam pipe (on the Ar side), main steam isolation valve (
Fil, (6) its main steam isolation valve (51,
(6) A water injection device consisting of a solid water injection pipe with a water injection isolation valve Qυ connected to a pressure water source (21) that injects enough water to seal the contact area between the poppet 0 barrel and the body 07). It is characterized by The above-mentioned pressure water source (20 is clean water stored in a tank (not shown) (condensate water from the turbine system can be used) can be easily obtained by applying Calo pressure with all pumps.

次に作用について説明する。Next, the effect will be explained.

原子炉通常運転時は、注水隔離弁(21)を閉鎖し、両
生蒸気隔離弁(51、+6+ ’e開放する。これがタ
ービン寄り主蒸気管(9)に破断部00)を生じた場合
には、両生蒸気隔離弁(5)、(61’z閉鎖し、注水
隔離弁Qりを開放して、圧力水源(囮から注水配管f2
2) ’lr介して、第1の主蒸気隔離弁(5)より上
流側の主蒸気管(力に注水し、ポペット(1〜とボデー
a′7)の接触部を水封する。そうすると第4図に示し
て説明したように主蒸気隔離弁(51、(6)からの蒸
気の漏洩が封入水により抑制さね、る。
During normal reactor operation, the water injection isolation valve (21) is closed and the amphibious steam isolation valve (51, +6+ 'e is opened.If this causes a break in the main steam pipe (9) near the turbine, , Amphibious steam isolation valve (5), (61'z is closed, water injection isolation valve Q is opened, and water injection pipe f2 is connected from the pressure water source (decoy).
2) Inject water into the main steam pipe (forced) upstream of the first main steam isolation valve (5) through the lr to water-seal the contact area between the poppets (1 to 1 and body a'7). As shown in FIG. 4 and explained above, leakage of steam from the main steam isolation valves (51, (6)) is suppressed by the sealed water.

向、本発明は上記し、かつ図面に示した実施例のみに限
定されるものではなく、例えば水の注入は、2個ある主
蒸気隔離弁(5) 、 (6)のうち、いずれか一方に
ついて行なうだけでもよい等、その要旨を震央しない範
囲で、種々変形して実施できることは勿論である。
However, the present invention is not limited to the embodiments described above and shown in the drawings; for example, water injection may be performed using either one of the two main steam isolation valves (5) and (6). Of course, it can be implemented in various ways without changing its gist, such as just doing the same thing.

発明の詳細 な説明したように、本発明によれば、主蒸気隔離弁より
上流側の主蒸気管に、主蒸気隔離弁閉鎖時にその主蒸気
隔離弁のポペットとボデーの接触部を水封する程度に水
を注入する水注入装置全接続したことにより、主蒸気隔
離弁は水で封止され、原子炉圧力容器内の放射能汚染蒸
気が漏洩するのを防止できる。これにより原子炉保護系
統、安全系の信頼性ヲ藁度に高め、引いては沸騰水形原
子力発電プラント全体の安全性、信頼性を向上する効果
がある。
DETAILED DESCRIPTION OF THE INVENTION According to the present invention, the contact portion between the poppet and the body of the main steam isolation valve is water-sealed in the main steam pipe upstream of the main steam isolation valve when the main steam isolation valve is closed. By fully connecting the water injection equipment that injects water to a certain level, the main steam isolation valve is sealed with water, preventing leakage of radioactively contaminated steam in the reactor pressure vessel. This has the effect of significantly increasing the reliability of the reactor protection system and safety system, which in turn improves the safety and reliability of the boiling water nuclear power plant as a whole.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は従来の主蒸気隔離弁の蒸気漏洩抑制装置會示す
配管系統図、第2図は従来(C用し本発明の一実施例に
も使用する主蒸気隔離弁を示す立面図、第3図および第
41凶はそれぞれ、異なる流体に対するシール性を示す
第2図のA部拡大断面図、第5図は本発明の主蒸気隔離
弁の蒸気漏洩抑制装置の一実施例を示す配管系統図であ
る。 l・・・原子炉圧力容器 5.6・・・主蒸気隔離弁7
.8.9・・・主蒸気管  17・・・ボデー18・・
・ポペット20・・圧力水源 21・・・注水配管    22・・・注水隔離弁23
・・水注入装置 代理人 弁理士  井 上 −男 特許庁長官 島 1)春 樹 殿 1.事件の表示 昭和56年特許願第190535号 2、発明の名称 主蒸気隔離弁の蒸気漏洩抑制装置 3、補正をする者 事件との関係 特許出願人 (307)東京芝浦電気株式会社 (ほか1名) 4、代 理 人 〒144 東京都大田区蒲田4丁目41番11号 第−津野田ビル 補正の対象 イ11   図   面 6、補正の内容 (1)第4図金利紙の通り訂正する。 以上 第  4  図 −515−
FIG. 1 is a piping system diagram showing a steam leakage suppression device for a conventional main steam isolation valve, and FIG. 2 is an elevational view showing a conventional main steam isolation valve (used for C and also used in an embodiment of the present invention). Figures 3 and 41 are enlarged sectional views of section A in Figure 2 showing sealing performance against different fluids, and Figure 5 is a piping diagram showing an embodiment of the steam leakage suppression device for the main steam isolation valve of the present invention. It is a system diagram. l... Reactor pressure vessel 5.6... Main steam isolation valve 7
.. 8.9...Main steam pipe 17...Body 18...
・Poppet 20...Pressure water source 21...Water injection piping 22...Water injection isolation valve 23
...Water injection device agent Patent attorney Inoue - Male Commissioner of the Patent Office Shima 1) Haruki Tono1. Display of the case 1982 Patent Application No. 190535 2 Name of the invention Steam leak suppression device for main steam isolation valve 3 Person making the amendment Relationship to the case Patent applicant (307) Tokyo Shibaura Electric Co., Ltd. (1 other person) ) 4. Agent Address: 4-41-11 Kamata, Ota-ku, Tokyo 144 - Tsunoda Building Subject of Amendment 11 Drawing 6, Contents of Amendment (1) Corrections will be made as per the Figure 4 interest sheet. Above is Figure 4-515-

Claims (1)

【特許請求の範囲】[Claims] 沸騰水形原子炉の原子炉圧力容器に設けた主蒸気隔雌弁
付王蒸気管の主蒸気隔離弁閉鎖時の主蒸気漏洩を抑制す
る装置において、主蒸気隔離弁より上流側の主蒸気管に
、主蒸気隔離弁閉鎖時にその主蒸気隔離弁のポペットと
ボデーの接触F!ivI全水封する程度に水を注入する
水注入装置を接続したこと全特徴とする主蒸気隔離弁の
蒸気漏洩抑制装置。
In a device for suppressing main steam leakage when the main steam isolation valve is closed in a main steam pipe with a main steam isolation female valve installed in the reactor pressure vessel of a boiling water reactor, the main steam pipe on the upstream side of the main steam isolation valve When the main steam isolation valve is closed, the poppet of the main steam isolation valve contacts the body F! ivI A steam leak suppression device for a main steam isolation valve, which is characterized in that it is connected to a water injection device that injects water to the extent that water is completely sealed.
JP56190535A 1981-11-30 1981-11-30 Steam-leakage suppressing apparatus for main steam stop valve Pending JPS5894677A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56190535A JPS5894677A (en) 1981-11-30 1981-11-30 Steam-leakage suppressing apparatus for main steam stop valve

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56190535A JPS5894677A (en) 1981-11-30 1981-11-30 Steam-leakage suppressing apparatus for main steam stop valve

Publications (1)

Publication Number Publication Date
JPS5894677A true JPS5894677A (en) 1983-06-04

Family

ID=16259697

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56190535A Pending JPS5894677A (en) 1981-11-30 1981-11-30 Steam-leakage suppressing apparatus for main steam stop valve

Country Status (1)

Country Link
JP (1) JPS5894677A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0321208A (en) * 1989-06-19 1991-01-30 Fuji Kiki Kogyo Kk Document stand
CN104930488A (en) * 2015-07-17 2015-09-23 东莞市菲腾电子科技有限公司 Equipment with steam generation device and capable of rapidly stopping steam spraying outside

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0321208A (en) * 1989-06-19 1991-01-30 Fuji Kiki Kogyo Kk Document stand
CN104930488A (en) * 2015-07-17 2015-09-23 东莞市菲腾电子科技有限公司 Equipment with steam generation device and capable of rapidly stopping steam spraying outside

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