JPH0333692A - Fast breeder reactor - Google Patents
Fast breeder reactorInfo
- Publication number
- JPH0333692A JPH0333692A JP1166687A JP16668789A JPH0333692A JP H0333692 A JPH0333692 A JP H0333692A JP 1166687 A JP1166687 A JP 1166687A JP 16668789 A JP16668789 A JP 16668789A JP H0333692 A JPH0333692 A JP H0333692A
- Authority
- JP
- Japan
- Prior art keywords
- region
- blanket
- reactor
- reactor core
- reactivity
- 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
Links
- 239000011734 sodium Substances 0.000 claims abstract description 21
- 239000000446 fuel Substances 0.000 claims abstract description 12
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims abstract description 3
- 239000002826 coolant Substances 0.000 claims abstract description 3
- 229910052708 sodium Inorganic materials 0.000 claims abstract description 3
- 230000009257 reactivity Effects 0.000 abstract description 19
- 239000011800 void material Substances 0.000 abstract description 13
- 238000009835 boiling Methods 0.000 abstract description 4
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract description 4
- 229910052778 Plutonium Inorganic materials 0.000 abstract description 2
- 229910052770 Uranium Inorganic materials 0.000 abstract description 2
- 239000007788 liquid Substances 0.000 abstract description 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 abstract description 2
- 238000006243 chemical reaction Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 230000004992 fission Effects 0.000 description 2
- 229910052695 Americium Inorganic materials 0.000 description 1
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical compound [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 description 1
- 230000000155 isotopic effect Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000009377 nuclear transmutation Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、超ウラン元素を核変換により消滅させる高速
増殖炉に関する。DETAILED DESCRIPTION OF THE INVENTION [Industrial Field of Application] The present invention relates to a fast breeder reactor that eliminates transuranium elements by transmutation.
従来の超ウラン元素を消滅させるための原子炉では、超
ウラン元素を炉心燃料に均質に混合し、炉内の中性子に
より核反応（核分裂及び中性子捕獲反応）させ消滅させ
る方法がとられている。なお、この種の装置として関連
するものには、例えば、特開昭６２−８９８号が挙げら
れる。Conventional nuclear reactors for annihilating transuranic elements employ a method in which transuranic elements are homogeneously mixed with core fuel and annihilated through nuclear reactions (fission and neutron capture reactions) using neutrons within the reactor. Note that related devices of this type include, for example, Japanese Patent Laid-Open No. 62-898.
上記従来技術は安全性の点について考慮がされておらず
、仮想事故で想定されるＮａボイド（Ｎａ沸騰）時の正
の反応度が超ウラン元素の混合により増大する問題があ
った。The above-mentioned conventional technology does not take safety into consideration, and there is a problem in that the positive reactivity at the time of Na void (Na boiling), which is assumed in a hypothetical accident, increases due to the mixing of transuranium elements.
本発明の目的は、正のＮａボイド反応度の領域の反応度
増大を抑えつつ、超ウラン元素を消滅できる高速増殖炉
を提供することにある。An object of the present invention is to provide a fast breeder reactor that can eliminate transuranium elements while suppressing an increase in reactivity in the region of positive Na void reactivity.
上記目的は、超ウラン元素を多量に混合する領域を中性
子漏洩の大きいブランケットとの境界の炉心領域とする
ことで達成される。The above object is achieved by setting the region where a large amount of transuranium elements are mixed in the core region at the boundary with the blanket where neutron leakage is large.
Ｎａがボイド化した時の反応度変化（Ｎａボイド反応度
）の炉心径方向位置に対する値を、第２図に示す。Ｎａ
ボイド反応度は、炉心中心領域では正の反応度であるが
、ブランケット境界では中性子の漏洩の影響が強く負と
なる。超ウラン元素を混合すると、超ウラン元素の方が
２８８Ｕ より核分裂反応が大きいため、中性子エネル
ギスペクトルが硬くなり、Ｎａボイド時の反応度も増大
する。FIG. 2 shows the change in reactivity when Na is voided (Na void reactivity) with respect to the position in the core radial direction. Na
The void reactivity is positive in the core region, but becomes negative at the blanket boundary due to the strong influence of neutron leakage. When a transuranic element is mixed, the nuclear fission reaction of the transuranic element is larger than that of 288U, so the neutron energy spectrum becomes hard and the reactivity in the Na void also increases.
しかし、ブランケット境界近傍では、中性子漏洩の寄与
が大きく、多量の超ウラン元素を混合しても、Ｎａボイ
ド反応度は小さく（炉心中心に比較して）抑えられる。However, near the blanket boundary, the contribution of neutron leakage is large, and even if a large amount of transuranium elements are mixed, the Na void reactivity is suppressed to a small level (compared to the core center).
以下、本発明の実施例を第１図、第３図、第４図、第５
図を用いて詳細に説明する。Embodiments of the present invention will be described below with reference to FIGS. 1, 3, 4, and 5.
This will be explained in detail using figures.
なお、ここでとりあげた高速増殖炉は、プルトニウムと
ウランの混合酸化物を装着した炉心燃料、主として減損
ウランをもつブランケット燃料が装荷され、冷却材とし
て液体ナトリウムを用いた場合のものである。また、超
ウラン元素は、軽水炉からの取出し廃棄物中に含まれる
ネプチニウム。The fast breeder reactor discussed here is loaded with a core fuel containing a mixed oxide of plutonium and uranium, primarily blanket fuel containing depleted uranium, and uses liquid sodium as a coolant. Another transuranium element is neptinium, which is contained in waste extracted from light water reactors.
アメリシウム、キューリラムの同位体元素、及び、その
組成割合を用いた。The isotopic elements of americium and curylum and their composition ratios were used.
本発明の高速増殖炉の一実施例の炉心垂直断面図を第１
図に示す。第１図において、炉心は、超ウラン元素の混
合割合を多くした領域１と少なくした領域２からなり、
領域１が径方向ブランケット３と軸方向ブランケット４
に接して配置される。A vertical cross-sectional view of the core of an embodiment of the fast breeder reactor of the present invention is shown in FIG.
As shown in the figure. In FIG. 1, the core consists of region 1 with a high mixing ratio of transuranium elements and region 2 with a low mixing ratio,
Region 1 is radial blanket 3 and axial blanket 4
placed in contact with.
次に、この構成に基づく効果を説明する。第３図は、本
実施例の高速増殖炉における、Ｎａボイド反応度の径方
向分布を従来例（超ウラン元素を炉心に均質に装荷した
高速増殖炉）と比較した囮である。本発明の炉心のＮａ
ボイド反応度分布は、炉心中央部での正の反応度値が小
さく、仮想事故時に炉心中央領域でのＮａ沸騰に伴う正
の反応度が小さく、安全である。Next, effects based on this configuration will be explained. FIG. 3 is a decoy for comparing the radial distribution of Na void reactivity in the fast breeder reactor of this example with that of a conventional example (a fast breeder reactor in which transuranium elements are uniformly loaded in the core). Na of the core of the present invention
The void reactivity distribution is safe because the positive reactivity value in the central region of the core is small, and the positive reactivity associated with Na boiling in the central region of the core in the event of a hypothetical accident is small.
次に、本発明の他の実施例について説明する。Next, other embodiments of the present invention will be described.
第４図は、超ウラン元素の混合割合の多い炉心領域が径
方向ブランケットに接する燃料集合体である炉心の垂直
断面図である。この場合も第１図の実施例と同様の効果
が得られ、燃料集合体の構成４−
が簡略化できる。第５図は、軸方向ブランケットに接す
る炉心領域の燃料に超ウラン元素の混合割合を多くした
炉心の垂直断面図である。超ウラン元素の混合割合で分
類した燃料集合体の種類が一種類となる。FIG. 4 is a vertical cross-sectional view of a core that is a fuel assembly in which a core region with a high mixing ratio of transuranium elements contacts a radial blanket. In this case as well, the same effects as in the embodiment shown in FIG. 1 can be obtained, and the structure 4- of the fuel assembly can be simplified. FIG. 5 is a vertical cross-sectional view of the core in which the fuel in the core region in contact with the axial blanket has a higher mixing ratio of transuranium elements. There is one type of fuel assembly classified by the mixing ratio of transuranium elements.
本発明によれば、超ウラン元素装荷時でも、Ｎａボイド
反応度のピーク値を低くすることができ、仮想事故時に
想定されるＮａ沸騰に基づく正の反応度投入量を低く抑
えることができる。According to the present invention, even when transuranic elements are loaded, the peak value of Na void reactivity can be lowered, and the amount of positive reactivity input based on Na boiling that is assumed in the event of a hypothetical accident can be kept low.
第１図は本発明の一実施例の高速増殖炉の炉心の断面図
、第２図は高速増殖炉の炉内Ｎａボイド反応度分布の説
明図、第３図は炉心の炉内Ｎａボイド反応度分布の説明
図、第４図および第５図はそれぞれ本発明の他の実施例
の炉心の断面図である。
１・・・超ウラン元素混合割合の多い炉心領域、２・・
・超ウラン元素混合割合の少ない炉心領域、３・・・径
第２図
（不８７↑／１直ン
第
図
（′ｐＨ： ） す戸ｌシ′ヂＩじワ＼らの柱オ
向ｓＬ離（千日７オイ厘ン
水産つヲン尼象
Ｃ７Ｆｔ縞）
第
図
第
図Figure 1 is a cross-sectional view of the core of a fast breeder reactor according to an embodiment of the present invention, Figure 2 is an explanatory diagram of the Na void reactivity distribution in the reactor of the fast breeder reactor, and Figure 3 is an illustration of the Na void reaction in the reactor core. 4 and 5 are cross-sectional views of the core of other embodiments of the present invention, respectively. 1... Core region with a high mixing ratio of transuranium elements, 2...
・Core region with a low mixing ratio of transuranium elements, 3...diameter 2nd diagram (un87↑/1 straight diagram ('pH: ) column facing sL Separation (1000-day 7-day fisheries Tsuone-ni-elephant C7Ft stripe) Figure Figure
Claims (1)
て、 ブランケットとの境界の前記炉心領域の燃料ほど超ウラ
ン元素の混合割合を多くすることを特徴とする高速増殖
炉。 ２、前記超ウラン元素の混合割合を多くする領域が径方
向ブランケットに接する燃料集合体である請求項１に記
載の高速増殖炉。 ３、前記超ウラン元素の混合割合を多くする領域が軸方
向ブランケットに接する炉心領域の燃料である請求項１
に記載の高速増殖炉。[Scope of Claims] 1. A fast breeder reactor characterized in that, in the core of a fast breeder reactor using sodium as a coolant, the mixing ratio of transuranic elements is increased in the fuel in the core region at the boundary with the blanket. 2. The fast breeder reactor according to claim 1, wherein the region in which the mixing ratio of the transuranium element is increased is a fuel assembly in contact with the radial blanket. 3. Claim 1, wherein the region in which the mixing ratio of the transuranic element is increased is the fuel in the core region in contact with the axial blanket.
Fast breeder reactor described in.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1166687A JPH0333692A (en) | 1989-06-30 | 1989-06-30 | Fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1166687A JPH0333692A (en) | 1989-06-30 | 1989-06-30 | Fast breeder reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0333692A true JPH0333692A (en) | 1991-02-13 |
Family
ID=15835876
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1166687A Pending JPH0333692A (en) | 1989-06-30 | 1989-06-30 | Fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0333692A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2679062A1 (en) * | 1991-07-08 | 1993-01-15 | Hitachi Ltd | Fast breeder reactor core and fuel assembly using such a core |
| US5299241A (en) * | 1990-08-03 | 1994-03-29 | Kabushiki Kaisha Toshiba | Transuranium element transmuting reactor core |
-
1989
- 1989-06-30 JP JP1166687A patent/JPH0333692A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5299241A (en) * | 1990-08-03 | 1994-03-29 | Kabushiki Kaisha Toshiba | Transuranium element transmuting reactor core |
| FR2679062A1 (en) * | 1991-07-08 | 1993-01-15 | Hitachi Ltd | Fast breeder reactor core and fuel assembly using such a core |
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