不同燃料循环方案的可持续性与经济性分析

丁文杰; 黄欢; 戴涛; 郭海兵

doi:10.11884/HPLPB201931.190013

不同燃料循环方案的可持续性与经济性分析

doi: 10.11884/HPLPB201931.190013

中国工程物理研究院核物理与化学研究所

基金项目:

国家自然科学基金项目 L172400024

详细信息

作者简介:
丁文杰(1990-)，男，硕士，助理研究员，主要从事反应堆热工水力研究; dwjcaep@163.com

中图分类号: TL249
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- 被引次数: 0
出版历程
- 收稿日期: 2019-01-15
- 修回日期: 2019-02-24
- 刊出日期: 2019-05-15

Sustainability and economy analysis of different fuel cycle options

Institute of Nuclear Physics and Chemistry, CAEP, Mianyang 621900, China

摘要

摘要: 基于核燃料循环政策技术的成熟度，选取了一次通过循环方案(OTC)、单次复用循环方案(TTC)、快堆闭式循环方案(FRC)及混合堆闭式循环方案(HRC)四种典型的核燃料循环方案进行分析。采用平衡物质流模型对不同燃料循环方案的可持续性进行研究，基于平准化电力成本计算方法对不同方案的燃料成本和乏燃料处置成本进行分析。研究结果表明：闭式燃料循环可极大减少核废料产生; 燃料可自持的FRC方案及HRC方案可使用贫铀做燃料而不消耗天然铀; 仅考虑燃料成本和乏燃料处置成本时，HRC方案的经济性最高而TTC方案的经济性最差。
- 燃料循环 /
- 平衡物质流 /
- 可持续性 /
- 平准化电力成本 /
- 经济性
Abstract: Based on the technology maturity, four typical nuclear fuel cycle options, namely, OTC, TTC, FRC and HRC, were selected for analysis. The sustainability of different fuel cycle options was studied using the balanced mass flow model, and the fuel cost and spent fuel disposal cost of different options were evaluated based on levelized cost of electricity calculation method. The results show that closed fuel cycle can greatly reduce the production of nuclear waste. And the FRC option with fuel self-supporting as well as the HRC option can use depleted uranium without consuming natural uranium. Besides, the HRC option is the most economical while the TTC option is the worst, considering only fuel cost and spent fuel disposal cost.
- fuel cycle /
- balanced mass flow /
- sustainability /
- levelized cost of electricity /
- economy

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图 1 OTC方案物质流计算示意图

Figure 1. Schematic diagram of mass flow calculation in the OTC option

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图 2 天然铀需求量与贫铀产生量

Figure 2. Natural uranium demand and depleted uranium production

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图 3 核废物产生量

Figure 3. Production of nuclear waste

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图 4 不同循环方案的平准化电力成本

Figure 4. Levelized cost of electricity in different cycle options

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表 1 轻水反应堆装料质量流

Table 1. Light water reactor loading mass flow

nuclide	mass flow/(MTHM·GWe^-1·a^-1)
	PWR UO₂		PWR MOX/UO₂
	load	after cooling	load		after cooling
	load	after cooling	MOX	UO₂	MOX	UO₂
HM	19.5	18.494	5.719	13.667	5.425	12.964
U(²³⁵U)	19.500(0.825)	18.244(0.150)	5.22	13.667	5.041	12.788
Pu	0	0.225	0.491	0	0.343	0.157
MA	0	0.025	0.008	0	0.04	0.02
TRU	0	0.25	0.499	0	0.383	0.177
FP	0	1.006	0	0	0.293	0.703

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表 2 快堆装料质量流

Table 2. Fast reactor loading mass flow

nuclide	mass flow/(MTHM·GWe^-1·a^-1)
	fast breeder reactor		fast burner reactor
	CR=1.23		CR=0		CR=0.5		CR=0.75		CR=1
	load	after cooling	load	after cooling	load	after cooling	load	after cooling	load	after cooling
HM	14.84	14.01	2.78	1.906	6.194	5.324	8.203	7.327	11.19	10.34
TRU	1.287	1.507	2.741	1.866	2.064	1.667	1.74	1.575	1.552	1.571
U	13.52	12.47	0.039	0.04	4.13	3.647	6.463	5.752	9.64	8.763
FP	0	0.831	0	0.874	0	0.87	0	0.876	0	0.857
Pu	1.287	1.507	-	-	-	-	-	-	-	-

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表 3 前端燃料单元的价格

Table 3. Price of units of front-end fuel

unit	reference value/(＄·kgHM^-1)
natural uranium	100
depleted uranium	10
conversion	10^a
concentration	140^b
UOX fabrication	258^c
MOX fabrication	2 400
fabrication of fast reactor fuel	2 400
fabrication of hybrid reactor fuel	30^d
Notes： a：The conversion price of recycled uranium is about 300% of that of the natural uranium; b：The enrichment price of recycled uranium is about 110% of that of the natural uranium; c：The manufacturing price of REPUOX fuel is about 107% of that of the natural uranium; d：The fuel for the hybrid reactor is a plate structure and requires no fine processing, so the manufacturing cost is low, but there was no mature technology. Referring to the conversion process of recycled uranium, the manufacturing cost of the hybrid reactor fuel was set to 30 ＄·kgHM^-1.

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表 4 燃料处置单元的价格

Table 4. Price of units of fuel disposal

unit	reference value/(＄·kgHM^-1)
UOX temporary storage	200
MOX temporary storage	200
UOX spent fuel disposal	412
MOX spent fuel disposal	3 130
UOX HLW	190
fast reactor HLW	280
UOX reprocess	1 600
fast reactor fuel reprocess	3 200
simple dry processing	120^a
Notes： a：The cost of fuel temporary cooling and storage was included in the cost of fuel reprocessing. The hybrid reactor fuel was reprocessed every five years by the simple dry process, to remove the fission products of spent fuel using the decay heat. The process was simple and required little cost, but there was no mature technology. Referring to the price of dry storage in EPRI, the price of simple dry process was set to 120 ＄·kgHM^-1

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