JPH0656425B2 - High conversion heavy water reactor - Google Patents
High conversion heavy water reactorInfo
- Publication number
- JPH0656425B2 JPH0656425B2 JP62247701A JP24770187A JPH0656425B2 JP H0656425 B2 JPH0656425 B2 JP H0656425B2 JP 62247701 A JP62247701 A JP 62247701A JP 24770187 A JP24770187 A JP 24770187A JP H0656425 B2 JPH0656425 B2 JP H0656425B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- water reactor
- high conversion
- heavy water
- reactor
- 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.)
- Expired - Fee Related
Links
Classifications
-
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 ［産業上の利用分野］ 本発明は、転換比が０．８以上で高燃焼度を達成できる
重水炉に関し、更に詳しくは、高転換軽水炉（ＨＣＬＷ
Ｒ）並の転換比をもち、軽水炉と同等の燃料集合体構造
を有する高転換重水炉に関するものである。Description: TECHNICAL FIELD The present invention relates to a heavy water reactor capable of achieving a high burnup at a conversion ratio of 0.8 or more, and more specifically, a high conversion light water reactor (HCLW).
R) The present invention relates to a high conversion heavy water reactor having a similar conversion ratio and a fuel assembly structure equivalent to that of a light water reactor.
［従来の技術］ 軽水炉から高速増殖炉への原子力開発基本路線の中間炉
的役割を果たすものとして高転換炉の開発が期待されて
いる。現在検討されている高転換軽水炉（ＨＣＬＷＲ）
は軽水炉の一種であり、減速材である軽水と燃料の体積
比率（Ｖm ／Ｖf ）を小さく（約０．５程度）すること
により中性子エネルギースペクトルを高エネルギー側に
シフトさせ、主に 238Ｕの共鳴エネルギー領域での吸収
量を増加させ、それによって今までの通常の軽水炉より
も 239Ｐｕの生成量を増大させ転換比を大幅に向上させ
ようと言うものである。[Prior Art] Development of a high conversion reactor is expected to play a role of an intermediate reactor on the basic line of nuclear power development from a light water reactor to a fast breeder reactor. High conversion light water reactor (HCLWR) currently under consideration
Is a type of light water reactor, shifting the neutron energy spectrum to the high energy side by volume ratio of the light water and the fuel is moderator (Vm / Vf) Decrease (approximately 0.5), mainly 238 U It is intended to increase the absorption amount in the resonance energy region, thereby increasing the production amount of 239 Pu and increasing the conversion ratio significantly as compared with the conventional light water reactor.
このような高転換軽水炉では０．８以上の転換比を達成
するために、燃料集合体内における燃料棒配列を稠密化
した六方格子（正三角形配列）とし、燃料棒間のピッチ
を小さくする必要がある。In order to achieve a conversion ratio of 0.8 or more in such a high conversion LWR, it is necessary to reduce the pitch between the fuel rods by using a dense hexagonal lattice (equal triangular arrangement) in the fuel assembly in the fuel assembly. is there.
［発明が解決しようとする問題点］ ところが燃料棒配列をこのように稠密化した六方格子に
すると、熱水力特性、例えば熱伝達特性や流動特性の変
動による原子炉熱出力への影響が予想されるし、冷却材
喪失事故時の再冠水評価を見直す必要が生じる。更には
燃料棒ピッチが狭くなるため燃料製造コストが増大する
等の欠点もある。[Problems to be Solved by the Invention] However, when the fuel rod array is formed into such a dense hexagonal lattice, the influence on the thermal output of the reactor due to fluctuations in thermal-hydraulic characteristics, such as heat transfer characteristics and flow characteristics, is expected. However, it will be necessary to review the re-flooding evaluation in the event of loss of coolant. Further, the fuel rod pitch is narrowed, so that there are drawbacks such as an increase in fuel manufacturing cost.
本発明の目的は、上記のような現在検討されている高転
換軽水炉が抱えている諸問題を解決し、転換比が０．８
以上で、しかも燃料集合体内の燃料棒配列は従来の軽水
炉と同等でよく、燃料集合体設計や冷却材喪失事故時の
再冠水評価の見直し等の必要がない高転換重水炉を提供
することにある。The object of the present invention is to solve various problems of the high conversion light water reactor currently being studied as described above, and to achieve a conversion ratio of 0.8
Above, moreover, the fuel rod arrangement in the fuel assembly may be the same as that of the conventional light water reactor, and to provide a high conversion heavy water reactor without the need to review the fuel assembly design and re-flooding evaluation at the loss of coolant accident. is there.
［問題点を解決するための手段］ 上記のような目的を達成することのできる本発明は、ウ
ラン・プルトニウム混合酸化物燃料を使用した燃料棒
を、通常の軽水炉と同等のピッチ（１．２〜１．５cm）
で正方格子状に配列し、減速材として重水を用いる高転
換重水炉である。[Means for Solving Problems] In the present invention which can achieve the above-mentioned object, a fuel rod using a uranium-plutonium mixed oxide fuel has a pitch (1.2) equivalent to that of a normal light water reactor. ~ 1.5 cm)
It is a high conversion heavy water reactor that is arranged in a square lattice and uses heavy water as a moderator.
従って本発明では減速材と燃料との体積比率（Ｖm ／Ｖ
f ）は例えば２程度であってよい。Therefore, in the present invention, the volume ratio of moderator and fuel (Vm / V
f) may be, for example, about 2.
［作用］ 本発明のように減速材（冷却材）に重水を使用すると、
重水の減速能が軽水のそれより劣るため、燃料棒の配列
が一般的な加圧水炉（ＰＷＲ）並（Ｖm ／Ｖf で約２）
でも０．８以上の高転換比が得られる。このため高転換
軽水炉のような燃料棒の稠密配列による問題を回避でき
ることになる。[Operation] When heavy water is used as the moderator (coolant) as in the present invention,
Since the deceleration capacity of heavy water is inferior to that of light water, the arrangement of fuel rods is similar to that of a general pressurized water reactor (PWR) (Vm / Vf is about 2).
However, a high conversion ratio of 0.8 or more can be obtained. Therefore, it is possible to avoid the problem due to the dense arrangement of the fuel rods such as in the high conversion LWR.
［実施例］ 第１図は本発明に係る高転換重水炉で用いる燃料集合体
の一実施例を示す断面図である。燃料棒１０はウラン・
プルトニウム混合酸化物燃料（ＭＯＸ燃料）を使用す
る。燃料棒１０の基本的な配列は加圧水炉と同等であ
り、比較的広いピッチ（１．２〜１．５cm）で正方格子
状に多数配列される。燃料集合体の中心には炉内計装用
案内管１２があり、また多数の制御案内管１４がほぼ正
方形状に分散配置され、その中に制御棒１６が挿入され
る。[Embodiment] FIG. 1 is a sectional view showing an embodiment of a fuel assembly used in a high conversion heavy water reactor according to the present invention. Fuel rod 10 is uranium
Plutonium mixed oxide fuel (MOX fuel) is used. The basic arrangement of the fuel rods 10 is the same as that of the pressurized water reactor, and a large number of fuel rods 10 are arranged in a square lattice pattern at a relatively wide pitch (1.2 to 1.5 cm). At the center of the fuel assembly is an in-core instrumentation guide tube 12, and a large number of control guide tubes 14 are arranged in a substantially square shape, and control rods 16 are inserted therein.
そしてこのような燃料集合体内には減速材と冷却材を兼
ねる重水が流通する。Heavy water that also serves as a moderator and a coolant circulates in such a fuel assembly.
このように減速材（冷却材）に重水を使用すると、重水
の減速能が軽水の減速能より低いため燃料棒のピッチが
大きく燃料体積に対する重水体積の比率（Ｖm ／Ｖf ）
が大きくても高転換比が得られる。本発明に係る高転換
重水炉におけるＶm ／Ｖf と転換比との関係を第２図に
示す。同図からも判るように現在の一般的な加圧水炉並
の燃料集合体構造（Ｖm ／Ｖf で約２）でも０．８以上
の高い転換比が得られることが判る。このことは高転換
軽水炉におけるような燃料棒の稠密配列の問題を回避で
きることを示している。When heavy water is used as the moderator (coolant) in this way, the speed of deceleration of heavy water is lower than that of light water, so the pitch of fuel rods is large and the ratio of the volume of heavy water to the volume of fuel (Vm / Vf)
A high conversion ratio can be obtained even when the value is large. The relationship between Vm / Vf and conversion ratio in the high conversion heavy water reactor according to the present invention is shown in FIG. As can be seen from the figure, it can be seen that a high conversion ratio of 0.8 or more can be obtained even with a fuel assembly structure (Vm / Vf of about 2) similar to that of a general current pressurized water reactor. This indicates that the problem of dense arrangement of fuel rods as in high conversion LWR can be avoided.
［発明の効果］ 本発明は上記のようにウラン・プルトニウム混合酸化物
燃料を使用した燃料棒を一般的な軽水炉と同等のピッチ
（１．２〜１．５cm）で正方格子状に配列し、減速材と
して重水を用いる高転換重水炉であるから、燃料棒の配
列ピッチが広いにも関わらず０．８以上の高転換比を達
成できる。EFFECTS OF THE INVENTION The present invention arranges fuel rods using the uranium-plutonium mixed oxide fuel as described above in a square lattice pattern at a pitch (1.2 to 1.5 cm) equivalent to that of a general light water reactor, Since this is a high conversion heavy water reactor that uses heavy water as a moderator, a high conversion ratio of 0.8 or higher can be achieved despite the wide array pitch of fuel rods.
従って燃料棒の配列を、現在検討されている高転換軽水
炉におけるような稠密化した六方格子配列に変える必要
がなく、このため熱水力特性や冷却材喪失事故時の再冠
水等の問題が無くなるし、その上燃料製造コストが増大
することもない。Therefore, it is not necessary to change the arrangement of fuel rods to the dense hexagonal lattice arrangement as in the high conversion light water reactor currently being studied, which eliminates problems such as thermal hydraulic characteristics and re-submersion in the event of loss of coolant. In addition, the fuel production cost does not increase.
第１図は本発明に係る高転換重水炉で用いる燃料集合体
の一実施例を示す断面図、第２図は高転換重水炉のＶm
／Ｖf （重水体積／燃料体積）と転換比の関係を示すグ
ラフである。 １０……燃料棒、１２……炉内計装用案内管、 １４……制御棒案内管、１６……制御棒。FIG. 1 is a sectional view showing an embodiment of a fuel assembly used in a high conversion heavy water reactor according to the present invention, and FIG. 2 is a Vm of the high conversion heavy water reactor.
6 is a graph showing the relationship between / Vf (heavy water volume / fuel volume) and the conversion ratio. 10 ... Fuel rod, 12 ... In-core instrumentation guide tube, 14 ... Control rod guide tube, 16 ... Control rod.
Claims (1)
用した燃料棒を、１．２〜１．５cmの燃料棒間ピッチで
正方格子状に配列し、減速材として重水を用いることを
特徴とする高転換重水炉。1. Fuel rods using a uranium-plutonium mixed oxide fuel are arranged in a square lattice pattern with a fuel rod pitch of 1.2 to 1.5 cm, and heavy water is used as a moderator. High conversion heavy water reactor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62247701A JPH0656425B2 (en) | 1987-09-30 | 1987-09-30 | High conversion heavy water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62247701A JPH0656425B2 (en) | 1987-09-30 | 1987-09-30 | High conversion heavy water reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6488396A JPS6488396A (en) | 1989-04-03 |
| JPH0656425B2 true JPH0656425B2 (en) | 1994-07-27 |
Family
ID=17167366
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62247701A Expired - Fee Related JPH0656425B2 (en) | 1987-09-30 | 1987-09-30 | High conversion heavy water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0656425B2 (en) |
-
1987
- 1987-09-30 JP JP62247701A patent/JPH0656425B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6488396A (en) | 1989-04-03 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| EP1085525B1 (en) | Light water reactor core and fuel assembly | |
| EP0856852B1 (en) | Reactor core for a light water cooled nuclear reactor and control rod for the same | |
| JPH058797B2 (en) | ||
| EP0093901B1 (en) | High uranium utilization fuel rod for light water reactors | |
| WO1985001826A1 (en) | Nuclear reactor of the seed and blanket type | |
| JPH067194B2 (en) | Light water reactor core and its fuel loading method | |
| US3212983A (en) | Neutronic reactor | |
| EP0051441A1 (en) | Nuclear reactor and fuel assembly therefor | |
| US4148687A (en) | Method for savings in nuclear reactors by using beryllium rods in fuel bundles | |
| JPH0339277B2 (en) | ||
| JPH0656425B2 (en) | High conversion heavy water reactor | |
| JP2713983B2 (en) | Reactor fuel assemblies | |
| JP2972177B2 (en) | Fuel element and fuel assembly for thermal neutron reactor | |
| JPH0415436B2 (en) | ||
| Jevremovic et al. | Design of an indirect-cycle fast breeder reactor cooled by supercritical steam | |
| JPH0636047B2 (en) | Fuel assembly for nuclear reactor | |
| JPS60201284A (en) | Fuel aggregate | |
| JP3318210B2 (en) | MOX fuel assembly and core | |
| JPH04301592A (en) | Fuel assembly | |
| JP3070756B2 (en) | Fuel assembly | |
| JP2510559B2 (en) | Reactor core | |
| JPH0631744B2 (en) | Boiling water reactor | |
| JP2632726B2 (en) | Fuel assembly for boiling water reactor | |
| JPH0452914B2 (en) | ||
| CA1100649A (en) | Method for savings in nuclear reactors by using beryllium embedded fuels |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |